Properties of Salt Important in Radioactive Waste Disposal

Bradshaw, R.L.; Empson, F.M.; Boegly, W.J.; Kubota, H.; Parker, F.L.; Struxness, E.G.

doi:10.1130/spe88-p643

Cited by 5 publications

(5 citation statements)

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“…The major conclusions drawn from these studies are : (5)(6)(7)(8) (1) The in situ heat-transfer properties of rock salt are sufficiently close to the values determined in the laboratory on single crystals that confidence can be placed on theoretical heat-transfer calculations. These studies have been concerned with heat transfer from the waste to the salt, effects of heat and radiation on rock salt, and the economics ofan actual disposal facility in a rock salt mine.…”

Section: Introductionmentioning

confidence: 62%

Project Salt Vault

Boegly¹,

Bradshaw²,

Empson³

et al. 1966

Health Physics

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The demonstration of the disposal of high-level radioactive waste solids has as its objectives the demonstration of required waste-handling equipment and techniques, the determination of the stability of salt under the influence of heat and radiation, and the collection of information on creep and plastic flow of salt which is needed for the design of an actual disposal facility.Fourteen irradiated fuel assemblies from the Engineering Test Reactor will serve as a source of radiation, since high-level solidified wastes do not exist at the present time. The assemblies will be placed in a circular array of holes in the floor of a newly mined area (14 ft above the existing mine floor,) with one can in the center and the other s i x canslocated peripherally,spaced 5 ft on centers. During the course of the 2-year test, four sets of assemblies will be used to achieve a peak dose in the salt of about 8 x lo8 rad and the temperature of the salt adjacent to the center hole will be maintained at 200°C with supplementary electrical heaters. A second radioactive array, located in the existing mine floor, will receive the fuel canisters which are removed from the main array at the end of each 6-month period. The purpose of this array is to study the problems which may be encountered if the waste containers are located in salt interbedded with water-bearing shale. A third array, consisting only of heaters, will be operated as a control to determine those effects due solely to heat.In addition to the radioactive and control arrays, a rib-pillar located between the main radioactive array and the control array will be heated electrically around its base to produce significant information on salt flow characteristics and mine stability at elevated temperatures.Preparation of the four experimental rooms will involve the mining of approximately 19.000 tons of salt. Placing of the first fuel assembly cans in the mine is expected to take place in November 1965. "

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Section: Introductionmentioning

confidence: 62%

Project Salt Vault

Boegly¹,

Bradshaw²,

Empson³

et al. 1966

Health Physics

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“…(13) This being the case, approximately 5 ft of solid salt or 74 ft of crushed salt (assuming 5 Q voids) will give adequate biological shielding to allow unlimited access to a room in a salt mine filled with the most radioactive waste of the future. (It is assumed that the containers are located in backfilled holes in the floor with the tops of the containers at the proper depth, and that container spacing is based on fission product-decay heat dissipation calculations).…”

Section: Resultsmentioning

confidence: 99%

Results of a Demonstration and Other Studies of the Disposal of High Level Solidified, Radioactive Wastes in a Salt Mine

Rl¹,

Fm²,

Wc³

et al. 1970

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The radioactive phase of the demonstration disposal of high-level radioactive wastes in a salt mine was completed by the end of June 1967. The remainder of the mine experiments were terminated, and The Carey Salt Company's Lyons, Kansas, mine was placed on a standby basis, beginning February 1968. During the 19-month operation of the radioactive demonstration, the average dose to the salt over the length of the radioactive container holes was about 8 x lo8 rads, and the peak dose was about lo9 rads. A study of the economics of disposal-in-salt was completed. The calculated cost per kilowatt-hour of electricity generated ranged from about 20 x lop3 to 2 x mill for wastes aged 1 yr and 30 yr, respectively. To summarize, it may be said that most of the major technical problems regarding disposal in salt have been resolved. The feasibility and safety of handling highly radioactive materials in an underground environment have been demonstrated. The stability 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 should make it possible to arrive at a suitable mine design for a disposal facility. A study of the economics of disposal in salt mines indicates that this method will be compatible with competitive nuclear power. All of these items combined leads one to the conclusion that burial in salt mines is one of the better, if not the best, methods for the ultimate disposal of high-level solidified wastes.

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“…When salt is heated to very high temperatures, it shatters. Bradshaw, et al (1968) suggested that the rise in pressure caused by heated brine inclusions is the major cause of shattering. The following tahle, taken from Bradshaw, et al (1968)…”

Section: Eventmentioning

confidence: 99%

“…Radiation has a minimal effect on the strength of salt. The following table from Bradshaw, et al (1968) lists the mechanical properties at 20 C°and 200°C for increasing increments of radiation dosage. The compressive strength of the irradiated salt is less than the unirradiated salt.…”

Section: Iv-27mentioning

confidence: 99%