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DISPOSAL OF HIGH LEVEL SOLIDIFIED WASTES IN SALT MNESA , 6
W. C. McClair., R. L. Bradshaw, and 7. M. Empsun
CFSTI PRICES
JUN : 3 1967
Health Paysics Division
Oak Ridge National Laboratory
Oak Ridge: Tennessee
- no. 13.00, un 65
Introduction
An experiment demonstrating the disposal of high-level radioactive
solid wastes, called Project Salt Vault, has been in progress since the
middle of November 1965. Irradiated fuel assemblies from the Engineering
Test Reactor, supplemented with electrical heat, are being used in lieu
of actual wastes. The objectives of the experiment are: (1) confirma-
tion of the feasibility and safety of waste disposal in salt mines; (2)
the demonstration of the waste-handling equipment and techniques, (3) de-
termination of the stability of salt under the influence of heat and ra-
diation, and (4) collection ci information on the creep and plastic flow
of salt.
The experiment was installed at the periphery of an inactive salt
mine, 1000 ft (300 meters) below ground, at Lyons, Kansas, and consists
of five rooms newly mined at a level approximately 15 ft (4.5 meters)
above the existing mine floor (Fig. 1). This increase in elevation was
necessary to assure that the holes in the floor into which the radioactive
Research sponsored by the U. S. Atomic Energy Commission under con-
tract with the Union Carbide Corporation.
For presentation at the IAEA Symposium on the Disposal of Radio-
active Wastes into the Ground, May 29 through June 2, 1967, Vienna,
Austria.
DISTRIBUTION OF THIS DOCUMENI IS UNLIMITED
LO
LEGAL NOTICE
This report was prepared us an account of Government sponsored work. Netthet dhe Dhutud
Statou, por the Commission, nor any person acting a behalf of the Countrion:
A. Makes any warranty or representation, expressed or implied, with post to the ment-
racy, completener, or watalness of the information contulmad ha tido report, or that the wo
of may information, apparatus, method, or proces disclosed to the report may not mortage
printly owned rights; or
B. Ananas nay Unblution with repect to the we of, or lor damag e d from the
use of way laformation, apparatus, method, or proces declared to the import
As und in the above, "person acting on behalf of the Comunindo wbude -
florue or coatractor of the Commission, or employee of such contractor, to the c h ut
auch employs or contractor of the Conniesion, or play of my contractor prepara
dienniaatas, or provides acceu to, nay taformation purpenal to Ho unploy or contract
with the Commission, or his employment with mucha contractor.
Fig. 1. Layout of Project Salt Vault Experimental Area (ORNL-DWG
63-744A).
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material was deposited would be dril cà into the purest available salt.
In adiitics to the rewly mined rooms, one room or the existing wire was
incorporated in the experiment in which the holes were drilled into a
2
floor which cortains appreciable quantities of shale. One of the new
experimental rooms is located directiy under the 20-in.- (50 cm diam
shaft from the surface used to lower the fuel assemblies into the mine.
The main part of the experiment is carried out in the two end
rooms of the experimental area and the room in the existing mine.
The
first experimental room contains the main radioactive array of seven
specially lined 12-ft- (3.7 meters) deep holes in the floor. Each of
these holes contains auxiliary electrical heaters and a canister with
two ETR fuel assemblies. The second room contains an electrical array
which is identical with the main array in every way except for the absence
of any radioactivity. This array provides a control for the main array,
and any differences in the rehavior of the salt can be ascribed to the
effects of radiation. The floor array is intended to investigate the
differences resulting from the presence in the floor of large amounts
of interbedded shale which contains several percent moisture. This part
of the experiment was undertaken so that the possibility of disposal in
old, mined-out areas could be considered rather than restricting appli-
.
cation of the method to mines specifically designed and excavated for
the purpose.
Operational Experience
The various operations involved in the handling of the radioactive
materials are shown on Fig. 2. The operation starts in a hot cell at
the National Reactor Test Station in Idaho where two irradiated ETR fuel
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Fig. 2. Simulated Waste Can Handling Operations (ORNL-DWG 66-15).
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PROJECT SALT VAULT –
MAJOR DESIGN PHASE
5. Storcce in Salt.
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assemblies, approximately 90 days out of tre reactor, are sealed into
a 6 'to (2 meters) 207., 5-5/3-in.- (15 cm) diam canister. Seven ci
these canisters are then loaded into the shipping cask which is transported
to the Kansac mine by truck, along with its self-contained cooling sys-
tem. At the mine, the cask is removed from the truck and erected 1a
vertical position over the waste-charging shaft. The canisters are then
lowered, one at a time, into tie mine thr:ugh the waste-charging shaft
where they are receiveå in the underground transporter. The transporter
then carries the canister to the experimental room and deposits it into
an awaiting hole. The relationship of some of these handling facilities
to the experimental area is shown pictorially in Fig. 3.
The first shipment of fuel assemblies was installed in the radio-
active array on November 15, 1965, which marked the beginning of the
experiment. In order to increase the total dose to the salt and to
gain additional experience with the handling equipment and techniques,
the canisters were exchanged for fresh ones every 6 months. In June 1966
the original seven canisters were moved to the floor radioactive array
and a new set was installed in the main array. In November 1966, the
original canisters were removed from the floor array and returned to
Idaho in exchange for a third set of seven new ones which were again
installed in the main array after transferring the second set to the
floor array. Since the objectives of the experiment, witr. respec'to
radiation dose and heating, have been met or exceeded, all fuel assemblies
will be removed from the mine and returned to Idaho in June 1967.
. Each canister contains approximately 200,000 Ci of activity when
it is received at the mine. All handling operations at the mine are
.
Fig. 3. Pictorial Representation of the Project Salt Vault Mine
Operations (OKNL-DWG-63-239-R2).
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WASTE D
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RAMP TO NEW WINE LEVEL
FUEL ASSEMBLY ARRAY
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NEW HIS LEVEL
147 ft ALOVE ExisiliiG MARKE FLOOR
DELIO:ISTRATIOI CF RADIOACTIVE SODIOS DISPOSAL II SALT
-
7
perforied by remote control without the aid o: 100 cells. The highest
IS
dose to any of the personnes during the candling operations so far com-
pleted was 200 mrad, to the head and hands or.y. Throughout the first
16 monühs of operation, there has been no accidental exposures nor any
accidental releases of activity to the off-gas system. ve feel that
the first two objectives of the experimer.t - the demonstration of tre
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feasibility and safety and demonstration of handling equipment - have
been successfully achieved.
Eifects of Heat and Radiation
The only distinguishable effect of radiation so far determined has
been the intermittent production of extremely swall quantities (less
than 1 ppm in the off-gas) of an oxidizing gas. The generation of this
gas, which is not radiolytic chlorine nor hydrogen peroxide, appears to
be a function of dose rate and dependent upon a tireshold salt tempera-
2-
ture of approximately 150°c .
Temperature distributions in the salt, as measured on the more
than 500 thermocouples throughout the experimental area, have reconfirmed
the validity of the theoretical conductivity calculations. 2,5 These
calculations make it possible to predict with reasonable accuracy the
temperature rise to be expected at any point in the salt around any
geometrical configuration of heat-generating wastes.
Some bedded salt, including that in Kansas, contains small amounts
(less than 1/2%) of moisture in the form of small intra-crystalline
AXA
brine inclusions.
This property had been assumed to liruit the maximum

:
8
allowable salt temperature to iess than 250°C; since, above that tempera-
ture, internal vapor pressure causes a violent shattering of the salt.
During the experiment, it was discovered that these brine inclusions
will migrate toward the heat sources under the influence of the thermal
gradients. Since a large volume of salt is heated appreciably, a con-
siderable volume of water is involved. Water has migrated into the ex-
perimental arrays located in the relatively pure salt at the average rate
of about 1 ml/day/nole. Although this quantity of water was not expected,
some of the problems associated with the inflow or water were already
under examination at the floor array. In this floor array the heat
sources were installed in material consisting of about 50% shale contain-
ing large amounts of water which is driven off by the heat. The rate of
water inflow at this array has been about 50 to 100 ml/day/nole. Addi-
tional tests concerning the consequences of the migration and inflow of
water are currently being carried out in the mine.
Structural Stability and Creep
Although laboratory tests indicated that some alteration of the
mechanical properties of salt occurs at doses above 5 x 20° rad, 4 no such
effect nas been discernable in the mine even though the total dose to
the salt around the main radioactive array is now approaching 109 rad.
However, the mechanical behavior of salt under the influence of elevated
temperatures and thermal gradients has provided the most startling ar.ů the
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most, interesting results from the experiment.
Sait exhibits plastic flow properties which are stronger temperature
dependicät. Laboratory studies carried out at Okivi or. model pillars of
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Lyons mines
ave yielded much information on this property which
can be summarized in the empirically determined strain rate equation,
é = 3.2 x 10-36 210.9 3.2 4-0.65
where
é = vertical (convergence) strain rate (10-6/r),
T = absolute temperature
o = uniaxial average pillar stress (psi), aná
t = time (hr).
However, because of scaling problems, this model work does not furnish
any information on the transient thermal stresses and the effects of
thermal gradients.
Some of the deformations of the salt around the main radioactive
array are illustrated in Fig. 4. These data are also typical of the
electrical (control) array. A constant heat generation rate of 1.5 kW
was maintained on each of the array holes by compensating for the de-
mental electrical heat delivered to each hole. The dashed curve on
Fig. 4 shows the temperature increase of the salt in the central region
of the array. The disrupting influence of the two exchanges of canisters
and the effect of an arbitrary increase in heating rate to 2.1 kw/nole
can also be seen. Curve i on Fig. 4 shows the uplift of the floor at
the center poinü oi the array due to thermal expansion of the salt. This
vertical movement of the floor was distributed across the room in the
SI
shape of a normal error curve, the limbs of which extend well beyond the
edges of the salt pillars supporting the room. This thermal expansion
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of the floor unäer the edges of the pillar caused an immediate acceleration
1-1
10
is. 4. Thermal Effects on Salü Arouna Experimental Rooms.
IC

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15669
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of the deformation of the pillar, the vertical component of which is
shown by the second curve on Fig. 4. Although an accelerated deforma-
tion of the pillars with heat was anticipated, several weeks are required
before there is any significant terperature increase in the pillar.
The immediate roof of the entire experimental area consists of a
22t- (60 cm) thick bed of salt which had separated from the overlying
material along a thin shale parting. Instruments in the area indicated
that this roof bed was sagging into the experimental rooms at the rate
of about 1/2 in. (13 mm) per year. Roof sags of this type are well-known
in salt mines, and this sag rate was not considered to be excessive.
As can be seen on curve 3, Fig. 4, the accelerated deformation of the
pillar was transferred to the sagging roof bed in the form of an axial
load which caused an immediate fivefold increase in the rate of sag.
Because of tre nature of the experiment and tae planned extensive
heating of the pillar in the center of the experimental area, roof bolts
were installed throughout the area to support the 2-ft-roof bed, even
though this accelerated sag by itself did not create a hazardous condi-
tion. The effect of these roof bolts is shown on the continuation of
curve 3 where it can be seen that the roof was lifteå slightly and the
rate of sag was reduced to about one-fourth of its original (preheating).
rate.
The experience with the roof bed illustrates several important points
t
pertaining both to the Project Salt Vault demonstration and to the oper-
ation of any háza-level-disposal facility in salt deposits. First, the
structural properties of salt are not completely understood, especially
their mechanical behavior at elevated temperatures and under thermal
Ć
es
gradients. With the present state of ino%ledge, it is impossible to
predict in detail all of the responses of the salt to any given set of
thermal conditions. Second, rock mechanics instrumentation should be
an integral part of any deep underground disposal experimentation or
facility. In the initial phases of such an operation, or whenever
there is any significant departure from established routine, this in-
strumentation shouid be fairly extensive so that (1) incipient structural
problems can be detected at any early stage, (2) sufficient information
will be available to enable the best solution to those problems to be
found, and (3) the solutions can be checked. After routine operations
01)
have been established, a limited member of zock mechanics instruments
should be maintained for proper control of the operation. Third, under-
ground mine disposal, in salt or any other formation, is still a mining
operation. The solutions to any problems shoulâ be sought first within
the body of existing mining technology.
A part of the Project Salt Vauli experimental program was designed
especially and exclusively in order to obtain additio.'al information
on the thermo-mechanical properties of salt under transient temperature
conditions. This is the heated pillar test where a 20-ft- (6 meters)
thick pillar between the two central rooms of the experimental area
(Fig. i) is being extensively heated by a total of 33 kw of electrical
power applied in the floor along the sides of the pillar. This con-
figuration represents approximately three times the heat input to the
ее
pillar which would be expected if the floor of the rooms were filied
with real solidified wastes.
The vertical deformation of this pillar,
as measured at seven gauge points, is shown in Fig. 5. The initial
portions of the curves represent the normal squeezing and plastic de-
formation of the pillar resulting from the overbuzden pressure. The
Sure.
Fig. 5. Vertical Deformation (convergence) or the Heated Pillar.

.
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middle part of the curves illustrate the effect of only one of the
heaters (adjacent to gauge 125) which was started as a preliminary to
the main experiment. Notice that the effect of this single 3-kw heat
source can also be seen at gauges 122 and 128, 20 ft (6 meters) array.
On Novembor 14, 1966 (standard day 1170), all 22 of the heaters
were turned on with a power input of 1.5 kw each. The resulting in-
crease in the rate of convergence of the pillar 18 about an order of
magnitude from 0.2 in./yr (5 mm) to 2.0 in./yr (5 cm). This rate of
convergence is approximately the same as would result from a doubling
of the overburden pressure or depth.
The strong temperature dependence
of the pillar deformation is further illustrated by the distribution
of the convergence around the pillar. The largest convergence and greatest
rate (gauges 125 and 128) occurs at the center region of the pillar which
18 the hottest. The least amount of convergence (gauges 128, 136, and
137) takes place around the end of the pillar where the heat losses to
the air result in the lowest temperatures.
Summary and Future Prospects
The experimental results from Project Salt Vault have been most
encouraging. The feasibility and safety of handling highly radioactive
materials ir: an underground environment has been demonstrated.
The sta-
bility of the salt under the effects of heat and radiation was shown,
as well as the capability of solving minor structural problems by standard
mining techniques. The data obtained on the creep and plastic flow
characteristics of the salt, especially from the heated pillar experi-
ment, will make it possiblė to arrive at a suitable mine design for a
15
disposal facility for any desired degree of room closure. A study of
the economics of disposal in salt matesº (assuming ü 30-yr interim
storüge) indicates that the cost oi? this ret..on will be approximately
0.002 mills/kwOut oi ti total waste managemeno cost oi 0.02 mills/xW:
All of these items combined leads one to the conclusion tha' burial in
salt mines is one of the better, i not the best, metrods for the uti-
mate disposal of high-level solidified wastes.
ci
.
.
..
--.--.
Based on this conciusion, an examination is now being made into the
desirability of establishing an actual disposal facility in the immediate
futwe. A brief descript:on of some of the salient points of this ex-
amination will illustrate what we consider to be the future prospects
of the method and its applicability in a rapidly expanding nuclear power
generation economy. The first nigh-level disposal facility could begin
by accepting waste pots from the Pacific Northwest Laboratories' Waste
.
..
-
-
-
---
Solidification Engineering Prototype facility which may become available
about 1970. This phase will anso provide an opportunity for working out
all legal, regulatory, political and public relation problems which
might develop. The facility shound have a built-in capability of ex-
ve
c+
pansion to meet the demands or the i'uel reprocessing industry and a
reasonably useful lifetime at or near full capacity. Since an interim
storage period of several years will be required, this expansion will
probably begin toward the end of the 1970's.
Projections of the future development of the nuciear industry' in
the United States indicates the largest installed capacities and the
CA
diren
.
greatest rate of growth will be in the Northeast Region and on the West
an online 7*
Coast, followed closely by the Southeast and the upper Vidwest Area.
Usable salt beds underlie (1) parts of Michigan, Northern Ohio, and
The that
*
CV
Western New York; (2) Certzal Kardam; (3) Scuinwesi Texus and new
lexico. The sali does arowd the Gum Coasü lüve beer. excluded from
this consideration, penuirs the invisi jäio oë jeme questions regard-
ing the suitačility of these structures.
Comparison, of tiie major waste source regions and troc availability
t
of disposal sites shows first the wsence of salt deposits in the Cali-
fornia area. Since transportation charges to Kansas or Texas will proba-
bly be prohibitive, soue other arrangements may have to be made. As one
possible solution to this problem, pians are now beirs made to examine
the feasibility of modifying the general sait disposal concept for appli-
cation in other geolojic materials, 20% example, thick ainyurite or lime-
stone beds. With regard to disposal ir salt taroughout the rest of the
country, two possibilities exist: (i) either a singie central disposal
facility located in Michigan or upper Appalachia which woulů receive
wastes from the entire section east of the Mississippi or (2) two facili-
ties with the first in Kansas, followed at a later time, dictated by demand,
by a second, probably in New York.
-*
-
- .
-
.
:
+ of
RUTEXERCIS
**
.
.
..
5
2
.
eu
. SCHAFTER, W. 7., et al., "Project Sült Vault: Design and Demonstra-
tion of Equipment," Proc. International Symposium on Solidification
and Long-Term Storage of Highly Radioactive wastes, Richland, Wash-
ington (Feb. 14-18, 1966) 685-705.
2. BRADSHAW, R. L., et al., "Project Salt Vault: Errects of Tempera-
ture and Radiation on Plastic Flow and Yine Stability," Proc. Inter-
national Symposium on Solidification and Long-Term Storage of Highly
Radioactive Wastes, Richland, Washington (Feb. 14-18, 1966) 702-722.
3. EMPSON, F. M., et al., "Project Salt Vault: Design and Operation,"
S
CA
Proc. International Symposium on Solidification and Long-Term Stor-
age of Highly Radioactive Wastes, Richland, Washington (Feb. 14-18,
1966) 671-684.
4. GUNTER, B. D., and PARKER, F. L., The Physical Properties of Rock
Salt as Influenced by Gamma Rays, ORNI-3027 (Varch 1961).
5. LOMENICK, T. F., and BRADSHAW, R. L., Accelerated Deformation of
Rock Salt at Elevated Temperature, Nature 207(4993) (July 10, 1965)
158-159.
6. BLOMKE, J. O., et al., "Estimated costs of High-Levei Waste Manage- .
ment," Proc. International Symposium on Solidification and Long-Term
Storage of Highly Radioactive Wastes, Richland, Washington (Feb. 14-
18, 1966) 830-843.
7. COWSER, K. E., BOEGLY, 'W. J., JR., and JACOBS, D. G., "Long Range
Waste Management Study," Health Physics Division annual Progress Re-
port for Period Ending July 1966, ORNL-4007, 37-39.
END
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DATE FILMED
7 / 20 /67






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