& # ºf . . . . - . . . 4 ºr -r rty,’ #iº, % ; - - ºft **** ; :#. # W. & &ze, 2.x. §§ §§ Wº: § §º . §§ºf sº, ſº ſ § 'º','! §: ºf, §§. º, "º º §§ - § §§ :: * º | EGAL NOTICE This report was prepared as an account of Government sponsored work. Neither the United States, nor the Commission, nor any person acting on behalf of the Commission: A. Makes any warranty or representa- tion, expressed or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information, appa- ratus, method, or process disclosed in this report may not infringe privately owned rights; or . - - . B. Assumes any liabilities with respect to the use of, or for damages resulting from the use of any information, apparatus, method, or process disclosed in this report. As used in the above, “person acting on behalf of the Commission” includes any em- ployee or contractor of the Commission, or employee of such contractor, to the extent that such employee or contractor of the Commission, or employee of such contractor prepares, disseminates, or provides access to, any information pursuant to his employ- ment or contract with the Commission, or his employment with such contractor. United States Atomic Energy Commi ssion Office of Technical Information TT"--—-------__ _* - - - **------...- --—- --~' USAEC Office of Technical Information Extension, Oak Ridge, Tennessee / mº sing: Raſtal Aſſiºn tº Date & September 12, 1949 & ” – 2 × . ----- : Subjects Contractor's Work Brief for the - ...? …” .* Materials Testing Reactor - To: Materials Testing Reactor Steering Committee From: Re Me Jones Before reading this document, please sign and date below: Itsmºſ D. This document contains restricted data as .#, - *** **..". Atomic Fnergy Act of 1946. $ºf t £: : * º º É CAUTHQN This document contains information affecting the ** { } { . . . . ſºational Defense of the United States. ... !- $3.3 ± e. * 3 # * : - *..." - e º º e - 3 # & fº y £: fºransmission or the disclosure of its contents 7:8: . …” in any manner to an unauthorized person is ºr i. i. i. tº- fº tº: * -r- tº & & *. º w º ; : r’ .." -: fi ſº - º hibited and may result in Severe. criminal pen- - i. #3 . !º 54 Kºź alties under applicable Federal laws. # 3 ## *- : ** - fi, fºr -ij. was tº * - . - º,f ...º.º. . ... - . . . - £8, *** **, ** ºw sº * * * º *, * ... * r; , ,w - § Fºg º *: * * * * * * * * * * * * * . . . . § {T}. * * * • 3' * : " ' I , -" - £3 * ‘. . . ; c. s * : 3 : * : *, *, st t * f. * . . . . ; * * * ..., , . . .” ...: r; + § & ty * ſ º ... . - . •. } y ...; ... ', s # § ; #. 3 ... ." ; : '. : ; § * ** *...* ... 'i ... # * *... . . '. # j : * * * § 3 ;...! i - . . . . !. ** -- - jºi...Sy:Firſ * ºi...ºf $$. §. PREFACE In order to place certain important information in the hands of the Materials Testing Reactor design-contractor at the earliest possible time, this report is being issued without particular data originally scheduled for incorporation. It is planned to issue the filing dates Of the MTR design reports in Appendix C and Figs , 3 and 4 of Appendix B at a later date o As the necessity arises, additional information may be autºited in the form of appendices relating to responsibilities, required approvals, design changes, and progress reports. Acknowledgement is made of the contributions to this report by • - John R. Huffman and Stuart McLain relating to the MTR design and develop- ment programs at Argonne National Laboratory. Re Me =7 . ... " § CAUTION This document contains information affecting the - 3. RE ST º f National Defense of the United States. \; - sº º, e." Sº, Å Its º or the disclosure of its contents º ſh ... . . . . in, any manner to an unauthorized person is pro- This do "mºnt contains restricted data as - hibited and may rºsult in s err criminal pen- defined in ... . . . . “...y...c. of 1946. - *ties under applicable Federal laws. RMJ #eg | CLASSIFICATION_gANCELLED Dare 1927-33 For The Atomic Energy Commission —r f 2 | 7%, ’, Qawas. . ** ** ...” * *) A à ū 3. - § ~,”, AA A*...*-*. •-dº Chief. Declassification Branchº_* exº" * , * e." '? () 3 0.0 lo,0 2.0 360 INDEX Section Page ABSTRACT 6 INTRODUCTION 7 lel History and Background of the MTR 7 le2 Summary of Pre-contract Program 8 CRNL-ANL PRE=CONTRACT DESIGN AND DEVELOPMENT PROGRAM 10 2el Design Program = 1946 to November, 1948 - LO 2 sll The Heavy Water High-Flux Pile 10 2012 The Light Water High-Flux Pile 10 2.13 The High-Flux Pile Mock-up 12 2.14. The Materials Testing Reactor i 12 2.2 MTR Design Program, November 1948, to Present 13 2.21 Present Status of Design Program in Pile 17 Structure and Reactor Tank 2622 Present Status of Design Program in Reactor 18 Building and Auxiliary Facilities 223 ORNL Reactor Development Program 20 2,31 Fuel Assemblies 21. 2,32 Beryllium Metallurg 2l 2633 Corrosion - 22 2,34. Heat Transfer - 22 2.35 Shielding - 23 2.36 Chemical Development 23 2.37 High-Flux Pile Reactor Tank Mock-up 24. J - 224. ANI. Reactor Development 25 EXECUTION OF DESIGN FOR CONSTRUCTION 27 3.1 (RNL-ANL - MTR Organization for Pre-Contract 27 Studies 3.22 Education and Orientation Program 27 3.3 The MTR Design Report 29 3o4. Reports Bearing on the MTR - 30 365 Drawings on the High-Flux Pile 31 3,6 Currently Active Drawings on the MTR - 31. 763 C93 • *.*, *, *, *.*.*, *. . . . . *"...º. Index (Cont.) APPENDIX A Index of Currently Active Drawings on MTR APPENDIX B Organization Charts APPENDIX C Schedule of MTR Design Reports APPENDIX D Bibliography of Reports Bearing on MTR APPENDIX E Index of Drawings on High-Flux Pile APPENDIX F Index of Terminal Reports on the 1000 Project by the Kellex Corporation - - - Page 32–33 34-35 36–38 39-44. A 5-50 51–52 -ie º wº. -- -- - - 0.0 Abstract - This report constitutes an introduction to the Materials Testing Reactor Project, written especially for the design contractor. The report is written in cognizance of the fact that it will be used largely by - personnel new to the technology of nuclear reactors. P Sufficient background and history are included to disclose the fundamental premises of the current design. Particular emphasis is placed upon a review of the pre-contract design and development programs in effect since the Materials Testing Reactor was initiated in November, 1948. A method of transmittal of technical data and specifications through the medium of MTR Design Reports is described, along with an education and orientation program for contractor's employees. 703 {}5 loC) Introduction lel History and Background of MTR With the termination of the war in 1945, the need of a comprehensive program of research and development in the field of nuclear reactors was clearly evident. The war-directed programs within tº amatten Project developed the basic principles of nuclear reactors; however, the proposals for peace time applications of atomic energy indicated the necessity Of - operation at higher radiation levels than those experiences on the plutonium production project. The peace time proposals for the application of nuclear energy Were primarily the generation of estanical work and the production of - radio-isotopes • In generating power, the relative availability of fission- able material dictates a high specific power (power per unit weight of fissionable material), which in turn produces a high neutron riz. The - advantages of higher neutron fluxes for isotope production are obvious from the standpoint Of production per unit time, particularly in the production of fissionable isotopes. It was then concluded that future reactors, for the most part, would be characterized by high neutron densities with correspondingly high radiation levels. In late 1945 the Oak Ridge National Laboratory, then Clinton Laboratories, initiated feasibility studies on a high flux research unit, from which, information could be developed for the design of power reactors and fissionable laterial - breederse 2ſ º:: * ‘. - . . .: ... + - “s:-- - * - - : - -- - º, -> º ºgº tº -- ** - Tº ſº. * †. * * * º º; ; º- • * - ºr . : - 3: . . . ºs ºr ...' : - ; ºr - . #. º - *-* *- - 2. - * . * : - * , -- iſ: In May 9 1946, a feasibility report was submitted on a heavy water unit similar to the Canadian machine at Chalk Rivere Even though the report indicated the unit to be feasible 9 using an enriched fuel for higher neutron flux, it was felt that better characteristics could te obtained in a light water moderated unit without the attendant complexities and expense of the heavy water unit. In early 1947, a feasibility study was completed to the point that • contractor was engaged to prosecute the detail design of a light-water—moderated; beryllium-reflected, reactor. The Commission's decision to consolidate its reactor program at the sºme National Laboratory terminated the design studies and contractor's work in Decembers l947, Development work nevertheless continued at Oak Ridge National Laboratory. Meanwhile 9 several groups within the Atomic Energy Commission were engaged in study of power generating reactors. The various reactors were all "high-flux" machiness with proposals of thermal and fast neutron fluxes higher than yet experienced on the projects As studies were reduced to more detail, the greatest unknown became the materials of constructione It is of course known from experience at Hanford that graphite undergoes considerable physical change under exposure to epi-thermal neutrons. This facts plus others, indicated again the necessity of a high neutron flux experimental toole le2 Summary of pre-contract Design Program In Novembers 1948, design studies of the Original high-flux machine were re-activated for proposal of a unit for testing and developing materials Of construction for nuclear reactors. By order of the Atomic Energy Commission to the Argonne National Laboratory, the Materials Testing Reactor was organized º*f | § f * 3: -º .-7-2s º.i as a joint project between the Argonne National Laboratory and the Oak Ridge National Laboratory. The joint responsibility is presently in effect, with the Oak Ridge National Laboratory bearing responsibility for the design of the reactor tank and its contents and the specifications of the pile structure. *some National Laboratory bears responsibility for the specifications of all other facilities related to the reactor. Responsibility for coordination of the programs at the two locations is vested in the Materials Testing Reactor Steering Committee; composed of the following people: Stuart McLaing Chairman, Argonne National Laboratory Marvin Mo Manns Project Engineer 9 Oak Ridge National Laboratory John Re Huffman; Project Engineers Argonne National Laboratory Since November, 1948, design and development programs related to the Materials Testing Reactor have been accelerated at both laboratories • A full scale mock-up of the High-Flux Pile reactor tank and its contents has been put into operation at oak Ridge and is presently undergoing test a Design of the reactor building and its exterior facilities is underway at Argonne whereas the experimental facilities and the pile structure are under study by the Oak Ridge staff. While all phases of the project are well along, considerable work remains in the testing of the mºck-up 3 particularly the control system, None— theless, it is felt that a design contractor may now take over the work and proceed with construction drawings, Studies at each of the laboratories will of course continue as the requirements dictate o : 220 ORNL – ANL Pre-Contract Design and Development Program 2.1 Design Program 1946 thru November, 1948 2ell The Heavy Water High Flux Pile - * - The prototype of the waterials Testing Reactor, called the High Flux Pile, was taken under study originally in late 1945, by the Technical Division of ORNL (then Clinton Laboratories). The unit was a light-water- cooled, heavy-water-moderated machine not unlike the Canadian pile at Chalk River. A report on the feasibility of the project 3 using an enriched fuel element, was submitted in May, 1946; (Report Mon!N-108). - It was recognized however 9 that many practical problems were involved which would require extensive development worke The complexities of the heavy water handling and purification system promised to be expensive; as did the reactor tank and its hundred odd through tubes and experimental - access thimbles. It was not certain that the proposed fuel elements were practical from the standpoint of fabrications and at the time of the report 2 there was insufficient heavy water available e The overall study indicated the unit to be feasible but extremely expensive and same vulnerable to damage. Further, the unit was so similar to the Canadian machine that its justification was debatable o - 2.12 The Light Water High Flux Pile In mid - 1946.9 scientists at the Clinton Laboratories suggested that caparable thermal neutron densities and higher fast neutron densities could be obtained with a light-water-moderated unit using beryllium metal &S 3. primary reflectore It was shown that with very thin sections or high velocity water cooline the fuel plates 9 the water could serve the dual purposes of moderator and coolante - 10 — & - - * - & º - t;2:4-fºr". . . . r" s , : -, -º-º: . . . . . . - - - : -. - # *. ‘... ** * • * . ... * ~ * - In view of this suggestion it was felt that a feasibility study should be made as a basis of comparision with the heavy water machine proposed earliero Design studies were initiated in October, 19469 and in April, 1947, the Process Design Information (Report Mons-262) was submitted to the Kellex Corporation as the basis for initiating design studies which would ultimately lead to construction drawings • Report MonP-272 was issued coincidentally on the physics of the units The work done by the Kellex Corporation was largely exploratory, Many phases of the design had not been considered in detail at the time the contractor was engagedo The feasibility of many of the proposed means was not clearly established; consequently, the contractor undertook feasibility studies and detail design proposals along with the laboratory personnel.• +: i a In late 1947, at the request of the Atomic Energy Commission, -—T *- a complete feasibility report was submitted indicating the status of each phase of the project and the proposed site plant (MonT-433.9 December 1, 1947), This report was 9 and doubtless still is 9 the most complete disclosure of the | High Flux Pile and its companion facilitieso On December 279_19473 the Atomic Energy Commission announced 2–~~ -— its decision to consolidate all reactor design at the Argonne National Laboratorye Design work on the High Flux Pile was consequently stopped at ORNL's although development work continued; and the contract with the Kellex Corporation was terminated. A list of the terminal reports tendered by the * Kellex Corporation is listed in Appendix E of this reporte 2.13 The High Flux Pile Mock-Up During 1948.9 as a part of ORNL's development programs the High Flux Pile Mock-Up was designed, "he reactor tank and its contents were designed and detaileds using a dummy reflector of aluminum rather than beryllium. This project was put into operation in April 9 19499 at Oak Ridge National Laboratoryo and while design studies on the pile proper had stopped, the design within the reactor tank was carried to completion as a part of the week-up programo - - 2.14 me Materials Testing Reactor " *. By order of the Atomic Energy Commission November 3, 1948, the High-Flux Unit was re-activated and re-named the Materials Testing Reactors signifying primary interest in construction materials for use in the Commission's broad program of reactor technology, Argonne National Laboratory was instructed to initiate the program as a joint effort with Oak Ridge National Laboratoryo The organization to prºsexute the design is shown in Figure le Responsibility for design and specifications were broadly established as follows: Detail design of reactor tank and its contents 9 including control elements and drives 9 top plug and bottom plug ORNI, Specifications within biological shield - ORNI, Specifications outside biological shields including site 9 reactor building 9 and all exterior auxiliaries — ANL Because of the interdependence of the various parts, the specified areas of responsibility are not as clearly cut as indicatede There are many "border-line" cases which have been particularly assigned in the Minutes of |- NOS\/[T] — — NOI I_\/WN HO + N | T\/] O|-||-|O Y A LI HOH_L^\/ /Nº) | STEJO\· /\ , ſr) /! © / _^ ^< \ _^`< \ .- ’ſ-Hº) N 3 TO}} d ’O OSS\/ -------------- B N V T] |’N I VNC]\/•-- }}I33|N|º)N3 || 23 TO? Jeff ~—~~~ NN\/WN- N\/WN}}|\/H D | 83BN10NE LO3rOdd — Nww.3.3.nH +|N NW7|WNNIV~12WN\7 VN H + [\ H- TIN B O BIB_L_LIWNWNOO @N I HIGIE LS~] N \/ ºD HIBE N | 3 WA – N N | Z →SHO LOBBIG T]NYJO Y TIN\/ | ‘O‘E ‘\/| ; ; " }* {}， { | } } | , ، ، ، ، ، ، ، ， ' } ( | } � 4 . + - * - -º- s: Wºº-Vºlºs tº 3. ". . . . . - * t ~. • • . - ~3. --- :: -º-, -z - the Fourteenth Meeting of the Steering Committees File Noe ANL-SM-269 dated June l; 1949e . Others will arise from time to time and will be assigned by the Committee e 2e2 MTR Design Program 9 Novembers 1948 to Present design programs reference should be made to report MonT-433.9 pages 5 through In order to best comprehend the following disclosure of the ORNL 8 inclusive; wherein a description of the pile proper is givene A brief study of this material will allow the reader to more readily grasp the essential features of the programo rapidly on the MTRo The earlier studies of the High Flux Pile allowed work to proceed The two reactors are fundamentally the same 9 with the significant changes being very few and appearing only in the experimental - facilitiese proper would be as follows: le 2e 3e 4e 5o 6e 7e Experimental facilities a Reactor Tank). Structural studies in Biological Shields It was decided that the order of design studies on the pile Primary service facilities (Pile water 9 airs special lines to Revision of Experimental facilities to meet practical limitations within Biological Shielde Detail design of graphite reflectors thermal shield. Design and specifications of special shielding and particular experimental facilitiese Specification of secondary service facilities (hot drains, power, vacuum, de-mineralized waters air, etc.) on exterior of concrete structures a lº - y S_2:** 3. 3. . . * * - ... : : :º.º. -- . . - ?’s.” ...... & " * . . . ." . As ... • * * * * * * .* * * : * * : * ~ * >, ~2: ...?. - . . . . " : -3.3'-º'--~ : – - *** -, *...* - : . . . . . . - * ** * - . . w * s … º- the above programo Meanwhile, the final design of the reactor and its parts within the Reactor Tank were delayed pending test and development in the mock-upe It should be noted here that this order of executing the job was chosen in an effort to maintain the experimental facilities as nearly as possible to the arrangement originally approved by the Committee as being the ideal arrangement. The philosophy has been to design the structure to the facilities, modifying the structure where at all feasible, rather than allow a conventional structure design to impose unnecessary limitations on the experimental facilities • The petuliar structural steel arrangement is a manifestation of this thinking rather than a unique design about which the other facilities were fittede - Toward arriving at a sufficient and reasonable design, the experi- mental and service facilities were reviewed and compared with what was con- sidered a most desirable structural steel design. Compromises in each of the parts were necessary's Certain facilities were moved to accomodate the steel frame-works and on the other hands the steel was modified peculiarly to accomodate certain facilities which it was felt could not be relocated. The resulting design in the pile structure is then a compromise of the following factors stated in the order of their importance 3 le Safe and successful operation of the reactore 2. Broad experimental utility with maximum flexibility, 3. Costs simplicity; and convenience of design, - As Ease of fabrication and assembly's 3.-- |st -i-:-:.--|- . .. In regard to the cost items every effort has been made to minimize special shielding in the concrete structure o The location of pile water lines and priºry service facilities has been governed tº proposing the use of ordinary concrete rather than the relatively expensive heavy aggregate concrete e Generally speaking, the effort has been to design for ordinary concrete in the structure above the first floor level; excepting around certain experi- mental facilities. While this contributes to some crowding of service facilities near the thermal ai-ia, it is felt that this is preferable to more generous spacing which would necessitate special shielding. Regarding the reactor tank and its contents, changes and improve— ments are anticipated as a result of the test program now underway on the Mock-ups It should be recalled that the mock-up is patterned after the High Flux Pile § consequently, the changes will include not only improvements but also the actual changes introduced in the MTRo The latter includes a 5 in a z 5 ins square hole through the reactor tank 9 removal of certain pre- matic shuttle tubes 9 a change in the elevation of the main beam holes, and a somewhat different assembly of the various reactor tank sections e As studies of the various sections of the pile structure are completed, - design reports are being written for use by the contractor. These "MTR Design Reports" will eventually serve as the main source of technical information for the contractor, . ... • ** . . .”. ~ * * ** ... • - Paralleling the design program at ORNL's the reactor design group at ANL has concentrated its efforts on the reactor buildings auxiliary buildings, handling equipment, cooling water system 9 air handling systems secondary service facilities, and the general site plan. In generals the design philosophy is to provide * facilities for the adequate use and operation of the reactor. Provisions for future expansions are being kept in mind in the overall planning, for as the experimental work with the reactor increases 9 facilities will doubtless be expanded proportionally, A brief study of possible construction schedules indicates that the reactor and reactor building will essentially dictate the project completion date; consequently 9 the major effort at ANL has been on problems directly or indirectly influencing the reactor building. The following is • a condensed outline of the design studies in progress at ANL8 te lo Reactor building, 20 Experimental hole plugs and related services a 3. Plug coffins and handling equipment in the reactor building, | 42 Discharge canal and canal handlings - $ 50 Control electrical network and control room layout a - 6. Water systems. 7o Air systemso e. Effluent control and radioactive storages 9e Site plan and service buildings a 10, Power distribution systems. . The first five of these have the greatest effect on the reactor building and its foundations. These items have therefore received the most attention. Considerable exploratory work has however been necessary on the other itemse > . . . - ... SECRET 703 ºf 6 SECRET . . While design reports on these buildings and facilities are planned, -. they will not be as definitive as those in preparation on the reactor structure, General requirements, specifications 9 pertinent data 9 and perhaps preferred design will be provided the design-contractor. It should be noted that many sº features of the design have not been 9 and will not be 9 determined in detail | until the design-contractor also has an opportunity to study theme Further- *. more, thorough esºnale studies, mia have not been carried out 9 may be i necessary in order to make certain decisions a | | 2021 Present Status of Design in Reactor Tank and Pile Structure | The experimental facilities were approved in principle by º * the Steering Committee on March 229, 1949, realizing that changes would | & necessarily require re-approval as the detail design materializedo The | primary service facilities were submitted May 16th, along with drawings º establishing the fundamental dimensions of the pile structure as a whole. With agreement in principle from the Committee on these points, studies were initiated on the structural steel frame work of the biological shields t The structural steel studies were carried only to the point of establishing the feasibility of bringing sufficient steel through the | congested area adjacent to the thermal shield to insure support of the reactor parts. rt is intended that the design contractor expand the design .. to include reinforcing steel and perhaps additional structural members as : | tº may be necessary in the outer portions of the biological shielde | . º, Calculations on the graphite cooling are well in hand, and | the detail design of the graphite structure is underwaye The thermal shield | design is approximately 85% completes the remaining work hinging on studies sº noa " related to heat production in the steele Designs of the thermal column and shielding facility are presently in process, - - - me following phases of the reactor design are either in a very preliminary stage or have not been started? - - - lo Liners in various experimental facility holese 2. The neutron Crystal spectrometer and the slurry experi- mental facilitieso 3. The vertical facility to be provided through the reactor active section in a shim-rod position, 4e Detail shielding around the experimental facility open- ings at the face of the structure; also special shield= ing in the biological shieldo 5e Exterior service failities serving the experimental facilities • 6. Revision of the reactor tank and its contents in accordance with changes in the MTR and developments in the Mock-Upe An index of the currently active drawings on the MTR is given in Appendix A of this report o ..) A 2.22 Present Status of Design in Reactor Building and Auxiliaries The present conceptions and design proposals for the facilities external to the reactor structure have been approved in Principle at various times by the Steering Committee, Final designs in many instances depend on exact site selection and site surveys which are not yet available. In addition 9 economic and engineering studies by the design-contractor will be necessary before final decisions are possible. The design of the reactor and laboratory buildings (1105A and B) as planned for the high flux research pile at ORNL has been revaluated. The effort has been to reduce costs; however, not at the expense of adequate - 18 - race for the use of the reactors Certain possibly desirables but not necessary, facilities have been reduced or eliminated from immediate ÇOſlº sideration. Several different studies have been completed and have resulted in a proposed design which appears to be satisfactory. No structural or architectural design has been undertaken, and economic evaluations of the different designs will be necessaryo While work has been in progress on the basement of the reactor building and on the discharge canal 9 not all the water lines 9 drain lines and similar service lines have been locatedo This phase of the work is progressing slowly since care is required to be sure that all facilities are providede - - The lengthy and detailed studies of experimental plugs, coffins for their removal and handling equipment have led to feasible designso since this type of work is closely associated with radioactivity and shield= - ing 9 the specifications are to be determined in detail. Only orientation studies have been in progress on the electrical control network and on the full control room layouto In many respects these problems must await information from ORNLo The site electrical distribution systems will depend largely upon information not presently available o Some general studies on effluent control and radioactive waste storage have been made • These subjects are under intensive study at several laboratories in the countrye Opinion favors delay in designing such systems for the MTR as long as possible until valuable data are available from these studies. Meanwhile, no more than minimum facilities should be a l'º - J provided for the start-up of the MTRo Present design contemplates much reduced facilities to those outlined in MonT-433. A revaluation of the water systems has been made in view of the move to Arcos Idahoo e spray evaporation method of cooling is still preferred, Raw water supply and treatment as effected by site conditions are under study. A large portion of design carried out by Kellex is still applicable, Functional layouts of the site plan have been prepared in order to establish broad requirementso In general segregation of facilities on the site into three areas is planned g a reactor area with provision for future expansion 9 a service area relatively free of radioactive effects; and a "hot" area where radioactive streams and wastes are handledo Both wind conditions and underground water streams must be studied carefullye 223 ORNL Reactor Development Program As a part of the high flux reactor program at out, four groups of technical personnel were engaged in study of problems related to the overall project. The groups were organized as follows: - (A) • Chemical Process Development (B) • Engineering Materials (Metallurgy) (C), Engineering Research and Develºpment (D). Reactor Physics At the height of the development program, approximately 150 technical and non-technical people were engaged in problems related to the high flux pileo This number diminished somewhat after the Commission's decision to transfer the reactor design program to Argonne, however, there are at present approximately 50 technical people working on problems related directly to the MTRo • … y {} g gº Ø Among the facilities now being used in development work at the laboratory are the following: (A) • Complete metallurgical laboratory. (B), Complete laboratory and rolling mill for the manufacture of uranium=containing fuel assemblies • - (C), Machine shop equipped for machining beryllium metal, - : (D), Fully equipped corrosion laboratory, (E) • Facility on the "X" Pile for studies of shielding materialso (F), Laboratory for studies of heat transfers (G), Hot Pilot Plant for investigation of 25 and 23 recovery. (H), Mock-up of the High-Flux Pile reactor tank, including mock º control systemo It is without the scope of this report to completely review the development program which has paralleled the design of the High-Flux Pile and the MTRo * It nevertheless may be of interest to review some of the more important projects which have been, and are presently, under investigations 2a3l Fuel Assemblies One of the first development programs undertaken in 1946 was the fabrication of the aluminum-clad uranium-alley plates into assemblies of 18 plates eache Coincidental to this problem was the similar fabrication of shim-rod 'fuel and absorber sectiºns. Both of the problems are well in hands and facilities are now available for the manufacture of three uranium-containing fuel assemblies per day. s 2.32 Beryllium Metallurgy - the fabrication of the beryllius metal reflector has long been regarded as one of the most serious problems inherent to the MTR design. - - - - ...º.º. - º: - - - = 2 | <--> º - “. - - - ‘. .. :- - - - - º {} º * ; - { - ** f -: * •º ... ºv *-*... ...? " *.*.* -º-, * * * • . . . . . .s” —a” . . . . .*, *.*.*.*.*.* -º Ǻ 24& - • *. -- - . • * g ' is . ...” - &’ • { ***, *: ... r.”: ... ." :* *...*.*.*.** *:::::: * Development work on this material has been carried on by installations of the AEC at M.I.T., Battelle, and Oak Ridge. In spite of the fact that the metal is extremely brittle as casts very hard, and difficult to machines even after extrusion for grain refinements the fabrication of the reflector as now conceived appears reasible. Studies related to sintered metal are receiving - considerable attention nowo This material machines with relative ease and can be made available in much larger sections than the extruded waterial. Until more data is available on its corrosion characteristics 9 the decision to substitute sintered metal is being withheld. 2.33 Corrosion A long range cºrrºsion program has been underway since late 1946. Data contained in the industrial literature were found to be lacking for conditions such as those expected in the reactor, consequently studies have centered mainly around tests which will allow reasonable prediction of the actions of ºrarious metals and metallic couples in the reactor coolant streame s - - Of particular interest in this program are the studies relating to corrosion product build up. This factor is of major importance in heat transfer 9 in flow of coolant through thin cooling passages, and in secondary stresses originating in corrosiona 20.34. Heat Transfer - The heat flux to be realized in the fuel assemblies of the MTR is perhaps the most remarkable engineering feature of the machine, considering the coolant temperature, pressures and the maximum fuel plate temperature permissible. The calculated maximum heat flux is approximately 595,000 BTU/ sq.ft./hres assuming the surface temperature of the fuel assemblies is not to exceed 233°F. Water velocities of 30 feet per second are planned in the fuel section; consequently, accurate values of the water film coefficient were tº- 22 C-> • r ,- - , s 6 tº - - if (, 3 tº 22 - - . ...; : P. 2 * S [[R f ... • ‘.... : ::::::::"a". . . .” --~" . . . . ...". . . . . . . ~ *.* :: * ~.… ." ... y “... ." . . - ... < *.* . .” -- . ." . - £3 - 2 .** º ‘.… necessary. Experiments at the laboratory have shown that water film coefficients of the order 7000 BTU/sq. fts/hro/*F may be realized, for which values scale coefficients of the order 25,000 BTU/sq. ft./hr/*F will have to be saintained in the fuel assemblies if their surface temperature is not to exceed 233°F. Toward investigation of this problems extensive heat transfer experiments have been conducted in conjunction with the corrosion studiese Studies have been made of the heat transfer characteristics of channels such as those in the fuel assemblies 9 and particular attention has been directed to water make-up which will reduce scaling to a minimums 2235 Shielding One of the objectives of the MTR is to provide facilities for interpretable testing of shielding materials at radiation levels not presently available. Meanwhile 9 there is presently a shielding study group *. conducting experiments on the "X" Piles Special materials are undergoing shielding tests whereby the economic aspects of the problem can be reconciled with the nuclear characteristics of the materialse Physical properties relating to strength 9 heat transfer characteristics 9 density 9 water content 9 and material and labor costs are other data being gatheredo 2e36 Chemical Development The extent of the chemical development program can be concluded from the fact that approximately two-thirds of all personnel engaged in develop- ment work are engaged in problems relating to the chemical separation of - . Uranium 235, uranium 2339 thorium, and the fission products. The relative availability of fissionable material again dictates the necessity of efficient 703 &23 --&”. º: º ºst- - - º: ºf - º # * tº f * ºf ºx - - - *: …" . . . * - - º ºr º - º - • * * *, *. - º *: t : ſº ". ... º. ---. - º: , “.. º “Tº • - ... :- - - , ---- r ...' . . . . * ". . " " . . . . . . : , T: ... . . . . _-- -- a senated means for the separation and re-processing of uranium fuel and the disposal of radio-active wastes. A process for the separation of uranium 233 from thorium is felt necessary in view of tº possibilities of breeder type reactors and the production of uranium 233 as a by-product radio-isotope * in the MTR. • * - The chemical separation plant will be designed for the MTR w on the basis of the development work now underway at ORNL. These processes were worked out in considerable detail for the High—Flux pile as outlined in Report MonT-433; howevers develerants of the past 18 months will allow considerable refinement of the original prºposals. 2.937 High-Flux Pile Reactor Tank Mock-Up In late 1946; the design of the reactor tank and its contents provoked many questions as regards mechanical operability. It was the considered - opinion of the laboratory that the cost of a full scale mock-up was justified from the standpoint of verifying operability, feasibility of fabrication of many parts 9 testing and development of the reactor control system 9 verifying the hydraulic characteristics of the machine, and perhaps checking criticality, Design was initiated in late 1947. Procurement was started in mid-1948 and the unit was assembled and put into operation in April, 1949. Testing has been started, and it is anticipated that investigation of the unit will extend into 1950. Meanwhiles refinement in the design of the MTR is being delayed pending the test datas & - - - Extremely valuable experience was gained in the course of fabricating the various partso Many improvements Weiſ's introduced while the material was in the vendors' shopse Particularly valuable data were taken # tº ºn 23, º {} … - . . ... r. . . . . -- . - - - * ... • - procedure. coincident to the test programs it is planned to try various improvements in the fuel assemblies 9 reflector, and control element drive water, and to design and develop remote handling tools which will be required in servicing the "hotº reactor. - * - . 224 ANL Reactor Development Program Since the development work on most problems associated With the re- actor has been under progress for so many years and is so well in hand at ORNL's no major experiments are planned at ANLa The project staff itself is not now sufficient in size to carry a large development program along With the design programe Since the physical plant at ANL is less than a year old 9 a backlog of experimental equipment has not been accumulated. However 9 sufficient spaces equipment and manpower can be procured for any experiment - which may be required. The project staff can call upon any division at ANL for assistance and experimental work within the limitations of each division's manpower and space o The various reactor design groups at ANL have frequent occasions to request such assistance 9 particularly from the Metallurgical Divisions the Electronics Section, the Chemistry Division, the Health Fºysics Divisions the Instrument Divisions and the Remote Control Engineering Division. Only one experimental project of any magnitude has been in operation at ANL, An investigation of the packing characteristics of graphite •º f £2% & & 5”. zºº.º.º.º. ****** * .ºr.3 ... "...". < * * * *.* • tº ". ... º. 2. ' - - - 4. - - & S. . - .** - *:- - - . - ... - * * 2-º'- e *... . . . . * s - rº":- * £2.2 . . . º * . - *... . . . . . . -- *:::::. . . . . . . ** * .. ** .*- *::... cz.:- * - “. . . ." .. ". *…* - :- pebble beds under thermal cycling has been completed. Incidental to the - main problems heat transfer and pressure drop data in such beds have been collected, - - As design progresses several mechanical features of various 43 facilities may require full-scale feasibility test so The following are examples of such experimental projects which might be initiated by ANL: le Tests of canal handling devices, 2. Construction and operation of experimental plugs and coffins. 3o Collection of data on pneumatic and hydraulic devicese 4, Warious performance tests cf proposed equipment e - 26 - ~ * 3.0 Execution of Design for Construction 3.l ORNL - ANL MTR Organization in Pre-contract Studies The organization for prosecution of the MTR design was discussed briefly in Section le?. Under the direction of the Steering Committee, ORNL and ANL are each assigned certain areas of responsibility. The design groups of each Laboratory then proceed with the design under the direction of the ; .fº--t|t|f# Project Engineero As conceptional layouts are completed 9 they are submitted through the Project Engineer for Committee approvale Actual design recommendations and proposals are likewise submitted for approvale Appendix B of this report contains Figures showing the general organizationai, sºname of each laboratory and the relation of the design groups to the overall organization, Names of personnel are included for introductory purposes. The Figures are listed here with 3 APPENDIX B - Fig. 1 ORNL - General organization Figo 2 ORNL - MTR Organization - Fige 3 ANL - General Organization Figo 4. ANL = Reactor Design Organization 3.2 Education and Orientation Program Past experience has shown the necessity of an organized program for the education and orientation of new personnele It is the established policy of both laboratories to provide its new employees with ample opportunity for study and instruction in the field of their assignment. Nuclear physics and reactor technology courses have comprised major portions of the educational program and have been offered periodically at ORNL and ANLe Their value has been evident in the interest and self application of new employeese 703 ± 27 It is the feeling of both laboratories that an organized Orientation program would be helpful to contractor's employees in order that the unique design problems in the MTR might be approached with a clearer understandingo An introduction to the peculiar nomenclature of reactor technology is required as well as a general review of the sary whys and wherefores of the designo It is felt that with such orientation 9 technical personnel could approach their assignments with more confidence 9 more freedom of judgment 9 and a better appreciation of the study and development which has gone into the designo Obviously 9 such a program annot be all inclusive am it. is not expected that the participants would finish such a program with the "state of the arts: well in hando Rather, it is to be hoped that at the close of the program, each participant would have a sºprehensive picture of the project 9 its aims 9 and a well rounded conception of the design study and development programs to the present a This orientation program could be made available at ORNL over a period of two weeks (ten working days). The main feature of the program would be a lecture series planned for seven days of the ten days program. Group discussions are regarded as an important part of a complete orientation and would be provided at the mid-point and at the close of the series. Outside the lecture periods, inspection tours of the development laboratories and the mock-up could be scheduled. Personnel of both laboratories would be available at all times to engage in informal discussions of questions arising in the minds of participants in the lectures and in the inspection of the - development facilitieso Participants with proper security clearances would be free at all times to visit development groups for discussion of special problems and to observe the work in progress. ºf tº 3 28 :* * - ...; - i. . . . . . . . . . . . . - rº, , r. º.ºrg: - . . . * < * * * > . . . . . . . - - * ... *** * * * * * - - - :* - - -, -; : :: . - ! ‘’’:. . . . . . . . . . . - •- - **~. '... -: . . . - - ºf * ----, * : ... " . . ;- - º :- r: : :: . . . . . . *** * * * -- ~ - - , .. :: *... . . . - - - - - * - wº - . . . - Regarding participation in the programs any contractor's employee with proper security clearance would be eligible. Participation would be left to the discretion of the contractore 3.3 The MTR Design Report In Section 2.15 of this reports reference was made to the MTR Design Reports. It is planned that this series of reports serve as the primary means of transmitting technical information. It is of course planned to schedule teamed conferences on the various phases of the MTR; however, it will be the purpose of the MTR Design Reports to convey as completely as possible all the pertinent information and sources of information available on a given subject. The schedule of these reports is given in Appendix C, indicating the subject 9 assigned mater, engineer or engineers in charges and scheduled filing date if the report is not already published. •º Inevitably there will be questions provoked by the Design Reports, It is planned that these questions will be discussed in technical conferences generally; however, as the design for construction progresses, information will be transmitted informally by technical personnel of the laboratories, perhaps by telephone in many cases, Regarding the transmission of design information outside the scope of the Design Reports 9 the following are to be considered the official and responsible sources for the general categories of the project listed below 3. Reactor Tank and contents 9 including control equipments • * * Top and bottom plugs, Discharge Chute 9 Monitor Tubes, Hydraulic Rabbits, etc. - - M. M. Mann, ORNL - - - - Project Engo 9 or his designated representatives ry {. ...} 2 {} :* . . .” • * , 'i, ‘. . . . . . ." ... --> * -, *:: **ś ...vºte: : * * *- : *, *. - \,, ºº, ºr - - - " " --~ * ... - . . . . ‘. ..., \ . . . . . . , - T. - . . ** * - , " . ~.4 – “... " * . . . ..., . . .'; - -- º - ; : y : * * . . . . "...: - * , , , z’ - - . * **...* * c. ** . . ". * , §§ -º “. . . . . : "º - - * * • 1 ºf nº a- ‘. . . . º -* . , 7 ". . . “A º º - * * ... - "... - - .*.-. : . . --- . . . -:. . . . . " - l" - * * : * > * * * * * * * . s \ . . - Concrete Structure surrounding Reactor, with exception of experimental plugso M. M. Mann; ORNL - - - •. Project Enge 3 or his designated representative • File Building, all auxiliary buildings, Water system, Air Systems and all other facilities outside Concrete structure. - === - J. Re Huffman, ANL gº - - - Proje Enges or his - - - designated representative. Information within the scope of the above categories will not be binding upon the design contractor or the responsible laboratory unless originated in the official sources listed. Border line cases of responsibility will be assigned by the Reactor Steering Committee as mentioned in Section 26 l/ke 3.24. Reports Bearing on the MTR - A list of reports directly related to the MTR design and development º are listed in Appendix D of this report. Many of the reports will be immediately recognized as obsolete. They are listed, nºtwithstanding, because of their historical value and the fact that some of the fundamental disclosures are yet valide - These reports are available from the central filing agency of the laboratory in which they originate. Requests for ORNL reports should be directed to No To Bray, Central Files, Oak Ridge National Laboratorye Requests for ANL reports should be directed to Dr. Hoylande Young, Argonne National Laboratory, Po 02 Box 52079 Chicago 809 Illinois. When reports are not . available through these agencies, the Project Engineer of the laboratory originating the report should be contacted directly with the request. sº 365 Drawings on High Flux Pile Early drawings on the High—Flux Piles while for the most part obsoletes will be of particular value in the orientation of contractor's employeese This list is given in Appendix E of this report. These tracings are on file in the Technical Division Tracing File at ORNL, Prints may be obtained by request to Mrs Ho Lo Watts 9 Technical Divisions when the tracing is not classifiedo :|;: : ..--. Classified prints may be requested through Mr. No To Bray, ORNL Central Files. 3.6 Currently Active Drawings on the MTR Currently active drawings on the MTR can be easily distinguished by § | - the DRP prefix on the drawing number. DRP drawings with serial numbers from l through 2999 originate at ORNLa DRP drawings from 3000 up originate at ANLo Procurement of prints of these drawings may be obtained from ORNL in the same manner as the High-Flux Pile prints described in Section 3.33. Requests for gº classified prints from ANL should be directed to Clyde A. Roberts, Argonne National Laboratory, Chicago's Non-classified prints may be obtained likewise. s . …º. APPENDIX A INDEX_0F_CURRENTLY ACTIVE DRAWINGS ON MTR Drawing . - - Number Title of Drawing Classification * Remarks DRP-ll Experimental Facilities – N–S Sectional Elevations Secret Pile Centerline. ... • - - DRP=ll, Experimental Facilities 9 Written Disclosure Secret Description by number of all experi- mental facilities . . DRP-15 Reactor Tank — Reflector Assembly-study Below HT.I. Secret, Layout study of reflector metal in and • * . - - - around HT-1 facility. - DRP-16 Reactor Tank - Reflector Assembly - Study 2 Below HT. l Secret, - Layout study of reflector metal, in and - - around HT-l. facility.o . - DRP-17 Reactor Shielding Facility, Sheets A, B, and Co Secret; Preliminary Layouts on feasibility of Shielding facility o DRP-18 Pile Structure - Fundamental Dimensions Secret Base dimensions of concrete structures including location of WG holes. DRP-19 Reactor Shielding Facility—Proposed Converter Plate Secret Preliminary Study layout for feasibility - : - report o • DRP-20 Reactor Shielding Facility-Basement Requirements Secret Primarily for use by ANL in planning . basemento DRP-22 Reactor Shielding Study Layout - Secret For estimate of shielding in and around - top and bottom plugs only o DRP=24. Experimental Facilities - Pile structure Secret Showing elevations of faces of pile - Elevation Wiews Structure • º DRP-25 Reactor Tank and Graphite Reflector - Fundamental Secret Base dimensions of tanks, and graphite, Dimensions - * - thermal shield, etco ------ d g-S ...; §§ \ º * º - ;...: '... TV, ºf , º, º 'º º “ . . & • . . . . . . , , ; º ... a ſº lºg - • ‘s º Ç tº W. #2 § ºf • ë • . . . . . s 6 É E * , * : *. [. * 25 - gi §º | § § º º ºr º, ... . . . . . . . . . .”... º.º. . . . .33:éºz.: . . . . . . . . . . . . . . .: ... , - . . . . . . . . . . . . . " * . . . . . . . . . . . - Šia.º.º.º. - !, • . - , * :"... . . . ; - - - - - - - - . . -ºx. . . . . . ...º.º. & isiºvisuasi-sº &lººks & sº §ºaºlºzssº • * ... ." N - --- :-1:... … ." Lºz.º.ºr. . . . tº: - '...'...' - - -*.*.*.*.*.*... ... v. ...?.: 13.4 . *... }... [...'...…...º.º.b.;12t...sº *...*.*.*.*- : *...*.*.*.*.*-> --> -ºu A-…º.º.º. * W. º º + A º - º n - - º - * º 4. ... ." gº º ... º a Fºl & § º - - i º .* E. :*. s ... • i...º. '''}; - - . . . . . . . . P - - x - | - - - - - * * Index of currently Active Drawings on MTR (cont'd) Drawing Number DRP-26 DRP-27 DRP=3]. DRP=32 DRP-33 DRP-34. DRP-35 DRP-47 DRP-48 s Title of Drawing Pile Structure – Shielding Facility Proposal Pile Structure - Horizontal Section Thru Sub-Pile - Room Pile Structure - Thermal Shields N-S Sectional Elevation - Pile Structure - Neutron Absorbing Curtain Pile Structure - Neutron Absorbing Curtain = Plug and Structural Detail Reactor Tank = Horizontal Section at Centerline of Beam Holes - Horizontal section at Pile Centerline - Experimental and Service Facilities Pile Structure - Structural Steel Proposal Pile Structure — Experimental and Service Facilities E-W Sectional Elevations = 33 - APPENDIX A (Cont'd) Classification Secret, Restricted Confidential Confidential Confidential. Secret Secret Secret Secret Remarks Composite of DRP-l'79 Sheets A,B, and Co Primarily for ANL, showing feasibility and requirementso Preliminary Layout of Neutron Shutter for Thermal Column and Shielding Facility o - Preliminary study of curtain structure. Showing typical fuel assembly 9 reflector pieces, clearances, etc. in tanko - - Section thru concrete structure at centerline of beam holes, showing all experimental facilities and service facilities super imposed on drawingo .#. - **** .. *:: | ºſ XIGIRIGI IAY | C | -3 • Çey $，? ſºs， ■ ■ ■ ·· *-S O | S \Hc] · |AIG INIyw kosmivlarTvDINHOBLsosae,\！} _|_S | WN 3 H2)H_LT] \/ IB HXº)OTTO||9* TvO1O3W || NOLLwiłł do`? '%) NIE NOLLCERBIG BALLO OBXE ĪĒĒĒĒĒĒĒĒĒĒĒĒĒĒĒĒĒ } } , }}·tº№ a XIIIīdāv a2 （º) | } 35 ALIDvavo Twnd, f{} 3. fºr " $ #ffffff || „NNwwww || „ENvivºSBNOC ‘W’8 || NOCHOD HWN LAOHOTITV1 BW||SLNEVNIHBEXE][SNÕTIVĪDIVO||NĒĒĒĒĒĒĒĒĀ|ĒīÕĪRĪõ5 |TOS NOO SEG TITI \/9) （}} /W ‘HONE TOHd B. LVIOossvºgāNV-Tºwn B B B N Iº) NB TOHOBT）, NNV VN 'WN 'WN NOI LVZINVOHO LOETOJE BIW į， º į Į į Ķ ē ; Tº) （) () \, MTR Design Report Noo l 2. 3 4. * 5 6 7 8, 9 º 15 l6 APPENDIX C SCHEDULE OF MTR. DESIGN_REPORTS Subiegº ORNL REPORTS Tank Sections A and Ee Graphite Reflector Air Cooling System Thermal Shield Structural Steel Neutron Crystal Spectrometer Slurry Experimental Facility Shielding Experimental Facility Thermal Column T-2 Wertical Hydraulics Reactor Experimental Facilities - General Pile Structure Pile Structure - External Service Facilities Monitoring System Reactor Control System - Exterior Design Data Sheets Instrument Holes — 36 — Je Fo Wo Wo Re Re Re Wo To To Jo Jo Wo Te Re De R. Engineer in Charge Pe Co Ee Ke Me Mo Ea Ho He Ro Ro Le H. Eo Jo Ee Scheduled Filing Date Gill Zapp Gall Sholl Browning Jones Jones Sholl Thomas Thomas McWherter McWherter. Scott, Thomas Engberg Mallon Engberg ;:º ſº nº T - - Sh - -- • - - ey *ś-- APPENDIX C_ (Conte) Mrs Design - Engineer in scheduled •" Report Noo Subject - - Charge Filing Date ANL REPORTS_ | s 20 Plugs - Sullivan i 21 Coffins Paleczny | 22 Handling of Coffins Schultz | 23 Canal Unloading and Loading Nicoll 24. Canal Handling Nicoli 25 Hydraulic Shuttles – 26 Pile Building - Guzik 27 Wing . . Guzik * 28 Water Supply Sivetz 29 Water Softening and Demineralizing Sivetz 30 Pile Process Water Sivetz 31 Cooling Water System Sivetz 32 Cooling Air System 33 Wentilation System for Radioactive Areas 34. Effluent Control 23 Burial ground 36 Layout of Stie Plan & - 37 Service Buildings & 38 Roads and Fences e 39 Future Expansion A0 Pile Network Kirby wº- rea '37- MTR Design Report Noo :: * . - ***...*. *~- ‘. . .aº APPENDIX g (Conte) Subject ANL, Reports Control. Rooms Primary Electricity Secondary Electricity Pneumatic shuttles Health Physics - 38 - Scheduled Filing Date Engineer in Charge Kirby Kirby Kirby Huffman yes O.38 Report Serial Number MonM-108 MonP–206 MonM-262 Monp-272 MonT-433 ORNI, A9–1-193 ORNL-8 ORNL–58 ORNL–l40 ORNL-215 ORNL-323 BIBLIOGRAPHY OF REPORTS BEARING ON MTR Title of Report Preliminary Process Design Report 9 1000 Project Physical Data on New High Flux Pile Process Design Informations 1000 Project Physics of the High-Flux Pile Feasibility Report on Clinton High-Flux Pile Radioisotope Production in Research Pile Brief of Development Reactor Project (MTR) Technical Division Report for period ending 3-1-48 Technical Division Quarterly Report for Period ending 6–1–48 Technical Division Quarterly Report for Period ending 9-1-48 Technical Division Quarterly Report for Period ending 11-30–48 - Technical Division Quarterly Report for Period ending 2–28-49 APPENDIX D Author Huffman & Leverett Weinberg Huffman & Leverett, Greuling 9 Soodak & Weinberg Huffman; Leverett et al. Erdman McLain Leverett McLain McLain Miller Miller ~ 39 = Date of Issue 5-15-46 ll-21-46 3-4-47 4–8–47 i2=i-47 6-6-47 l-l o-0 3-l-48 6–1–48 9-l-48 12–1-48 3–1-48 Remarke Preliminary Study on heavy water unit o For reference to High- Flux Pile only, Design data on light water-beryllium unit Memorandum For review by prospective contractorso © & t d t º F.s.º. § F- º º * 4. t §§ n * . . . - * . . • w - i ! * * - “, . $ } * - * W. , ' ' '... ." . . . . . . ; r; ‘. .” - * ... - * . . . * * * * - i. ***'. | + r th Title of Report º APPENDIX D (Conto) Author ORNL Physics Division Quarterly Reports ORNL Technical Divisiong Section IIIs Monthly Reports ORNL Technical Division, Section IV, Monthly Reportso Cost Estimate for the MTR Preliminary Cost Estimate for the MTR REACTOR COOLING General Description of Process Water System ORNL 48–7–312 ORNI, 49–1–281 ORNI, 49-A-l' & . . . . . º . ...tº Report Serial Number COST ESTIMATES 49-4-210 º ANL-SM-27 SYSTEMS ORNI, A-l.94. Pile Estimate of Air Cooling Requirements - Pebble Zone º Air Handling Facilities for the MTR Activities in Process Water Lane & Briggs Smith 9 Hinchman, & Grylls McCullough Air Cooling Requirements of the High-Flux Lane Wanſinkle Goeller Farmer Date of Issue 6-22-49 4–21-47 7-7–48 1-18-49 A-LA-49 4–7–47 Remarks Memorandum, For reference onlyo Preliminary survey only a For reference only. Will be revised for MTR. SECRET iaiuº *...; **** F-4 Report Serial APPENDIX D (Cont.) Number Title of Report Author ORNL * 48–6–155 Cooling After Shutdown Huffman 48–10–263 Cooling After Shutdown Lane ORNI, - A8-7-191 Natural Convection Cooling of Active Lane - Assemblies ORNL-120 Heat Dissipation from Fuel Assemblies stronquist after Shutdown ANL-TES-1 Emergency Cooling Water Requirements Sullivan ANL–JRH-6 Safety Provisions for Development Reactor Huffman ANL-JRH-11 Changes to Safety Provisions for Huffman Development Reactor ORNL 49–1-238 Shielding of Sub-Pile Room from Pile Water No Smith Activity ORNL 49–6–200 Shielding of Water Inlet Tubes Noderer ORNL - A9–3–91 Heat Transfer and Water Flow in Active sect. VanWinkle ORNL Aff-l.0–453 Pressure Differences between Un-equal Stromduist Annuli of Multiplate Assembly ORNL t Aff-9–307 Pressure Drop in Multi-plate assembly Stromduist - Al - Date of Issue Remarks 6-7–48 10-22-48 7–16–48 8-1-48 12-31–48 l-3-49 l—25-49 l—18–49 6–10–49 2–28-49 10–9–47 9-5-47 - • *.*. * . . . ºf . ''}~ : * * *...***** * ...º. * *. * * * *i.º. ( !. -ºſ.º.B.A-....... x: * -- - - -1. 1 ºã :-ºº: tº as :: *- : * * * 4}...", " ... Art-Lºvet, v. ... -: 1. 2...&#.4:21.4-k, -k-cºs r ....si. . .4.” •' ...... A 1. º.º.º. 4.4. , sº tº 3.34 º'º -15S-2-11.) $ . . SECRET • , " ...' * * - lit. APPENDIX_E (Conte) w Drawing • Number Drawing Title Classification TD=210 1000 Project - Pile Air System - Wertical Section Secret - - Thru B-1 Facility TD-211 1000 Project - Pile Air System — Vertical Section Secret - Thru Discharge Water Lines TD=2.12 1000 Project - Pile Bldg., - Basement Floor Plans Secret TD–220 1000 Project – Reactor Tank – Wertical Section Secret TD-221 1000 Project = Reactor Tank = Wertical Section Secret Thru Beam Holes TD=223 1000 Project - Pile Experimental Facilities - Section Secret at Horizontal Centerline º - TD=224 loC0 Project – Wertical Section along Thermal Columns Secret TD=226 1000 Project = Building Cross Section Showing Secret Basement and Canal A TD=240 1000 Project - Flowsheet of Cooling Water System Restricted TD=248 1000 Project = Flowsheet of Process Cooling Water Secret System TD-271 1000 Project – Fuel Assembly Secret TD=274 1000 Project — Sub-Pile Room Secret TD-295 1000 Project = Pile Experimental Facilities — Canal Secret Hot Lab Layout TD-309 1000 Project – Active Section – Horizontal Section Secret Showing typical fuel assemblies, shim- safety rods 9 reflector, etc., a 6–19–47 Remarks s of 4 ſº tº $ § #: º - º - ; º º t ; : * , £iº º Drawing 3, & 4 Confidential Secret Secret Secret Secret Secret Secret Secret Secret Secret Restricted Secret * *...* º!, - . . ; *-'. . i *...*.*.*.*.*.* *...*.*, *, *...*.*.x.J-4: 1.21'º'º ºv.ºn...” Classification Remarks As of lº-20-49. As of 2-8-49 $ 4 * * f * *- : * i g- f •, • * , *** * ---...* . .* . . . *:::::: • 3 'º - “. . . . . . . . . § . . . . . . . . . . . * * * : * > . . ...T. t ...’ s º 5, , ºf * : , S:.., . . . "Hi tº. “ ” - K . - * * * ºf • ‘;', * * * 1*, * 4. * * º ". . . . , - ~ ».” . . ". . * . . • * --- - at - Drawing Number TD=942 TD=1109 TD=l70 TD=1171 TD-1183 : : 2.`--º APPENDIX E_ (Conte) Drawing Title Classification . Project 175—R; Mock-up 9 Shim-Safety Control Rod Restricted Assembly - MTR Project - Fuel Assembly Production Flowsheet Secret, Project 175-Rs Mock-up Tank Assembly 9 with Top Plug Secret Project 175—R, Top Plug, Section A-A of Dwge TD-1170 Restricted Project 175–R; Monitor Tube Assembly Restricted - 49 – * * * * * * *-** . Remarks As of 3-4-49, As of 4-l 5-49. ' tº 4 MTR-301A–E MTR-3016–C MTR-3016–E MTR-3016–G Sho 3 of 6 MTR=3016–C She 4 of 6 MTR-3016–C Sho 5 of 6 MTR-3016–E Sho 6 of 6 MTR-3018-E CSK 100–7F 3' ey * Drawing Noo §º § * , : ; - - - -- ºf . , • * 4 ** ". . ... i t º - * * *** * . . * V •' r" | \, , º' ...; - . . . i-º,+','l','º' 4°13' ...:”). I *** , 3 : " , ",. . . . ." § - * * # CSK=104 •º Ç C. CSK-119-E - CSK-147 & :CSK-151 CSK-164—E ; i ... • '3% Drawing Title Plot Plan Proposal - Study #2 Proposal Reactor Bldg, Basement Floor Plan Study #4 Proposal Reactor Bldg., lst Floor Plan Study #4 Proposal Reactor Bldg., 2nd Floor Plan Study #4 Proposal Reactor Bldg., 3rd Floor Plan Study #4 Proposal Reactor Bldg., Wertical Section Study #4 - - Proposal Reactor Bldgo Isometric View Study #4 Proposed Beam Hole Liner - Cylindrical Type Development Reactor Cooling Water System Proposed for Maximum Safety Safety Provisions Horize Beam Hole Plugs Study #2 DoRo Po Tentative Process Water System Proposal-Beam Hole Plugs and Shields Horize Beam Hole Plugs Study #3 = 50= APPENDIX E (Conte) glassification None None None None None None None Secret Secret secret None None None Norie Active As Active as Active as Active as Active as Active as Active as Now Being Active as Active as Active a Active o Remarks of this date a of this dates of this date o of this date. of this date, of this dates of this date o Prepared a of this date o . of this dates Active for reference a ºf * Coro Noo 48–3–77 48–3–78 48–3–79 A8-3–80 48–3–8]. 48–3–32 48–3–83 48–3–85 48–3–86 A8-3–87 48-3-88 48-3-89 A8-3–91 48–3–92 48–3–93 APPENDIX F. HIGH-FIUY RESEARCH PILE Title Study Request Noo Hot Waste Disposal w 8 File Shield and Concrete 17 Graphite Arrangement l3 Contaminated Air System 16 Process Water Controls and Walving i l3 Reservoir Buildings ill2p 11049 ll08 lC) Cooling Towers 9 Pile Mock-up and Pile Tank "Y & 20 Pile Auxiliary Building l Demineralized Water Make-up System 3 Control Rods and Drives 6 & 21 Plot, Plan 2 Shim Rod Controls - 37 Retention Basin - - 15 Process Water Seal Tank 14 = 5l - Jano Deco Deco Deço Jan. Jano Jano Jano Jano Jano Jano Jane Jano Jano Jano King ºne of status abroats - study hºursts i Tim 37 Date of Dogument. 7, 1948 209 1947 30, 1947 209 lº/” 139 1948 69 l948 59 1948 13, 1948 5, 1948 14; 1948 23, 1948 12, 1948 6, 1948 12, 1948 5, 1948 Date of Issue March 5, 1948 5,1948 March March March March March wara March March March March March March March March 59 59 59 59 59 59 59 59 59 59 59 59 59 1948 1948 1948 1948 1948 1948 1948 1948 1948 1948 1948 1948 1948 Remarks S S::SRC © fr; U) 83! 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