Reaction of the Topopah Spring tuff with J-13 well water at 90{sup 0}C and 150{sup 0}C

AbstractCarbon steels may be used for borehole liners in a potential high-level nuclear waste repository in tuff in Nevada. Borehole liners are needed to facilitate emplacement of the waste packages and to facilitate retrieval of the packages, if required. Corrosion rates of low carbon structural steels AISI 1020 and ASTM A-36 were determined in J-13 well water and in saturated steam at 100°C. J-13 well water is representative of water which has percolated through the tuff horizon where the repository would be located. Tests were conducted in air-sparged J-13 water to attain stronger oxidizing conditions. A limited number of irradiation corrosion and stress corrosion tests were performed. Chromium-molybdenum alloy steels and cast irons were also tested. These materials showed lower general corrosion but were susceptible to stress corrosion cracking when welded.

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Report of the committee to review the use of J-13 well water in Nevada Nuclear Waste Storage Investigations

10.2172/137644 ◽

1990 ◽

Cited By ~ 25

Author(s):

J.E. Harrar ◽

J.F. Carley ◽

W.F. Isherwood ◽

E. Raber

Keyword(s):

Nuclear Waste ◽

Well Water ◽

Nuclear Waste Storage ◽

Waste Storage ◽

J 13

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Derivation of a Waste Package Source Term for NNWSI from the Results of Laboratory Experiments

MRS Proceedings ◽

10.1557/proc-50-337 ◽

1985 ◽

Vol 50 ◽

Author(s):

Virginia M. Oversby ◽

Charles N. Wilson

Keyword(s):

Laboratory Experiments ◽

Source Term ◽

Yucca Mountain ◽

Maximum Amount ◽

Well Water ◽

Pressurized Water Reactor ◽

Spent Fuel ◽

Pressurized Water ◽

J 13 ◽

Fractional Release

AbstractResults are presented for the dissolution of Turkey Point pressurized water reactor (PWR) spent fuel in J-13 well water at ambient hot cell temperatures. These results are compared with those previously obtained on Turkey Point fuel in deionized water, on H. B. Robinson PWR fuel in J-13 water, and by other workers using various fuels in dilute bicarbonate groundwaters. A model is presented that represents the conditions under which maximum dissolution of spent fuel could occur in a repository sited at Yucca Mountain, Nevada. Using an experimentally determined upper limit of 5 mg/l for uranium solubility in J-13 water, a fractional release rate of 6.4 × 10−8 per year is obtained by assuming that all water entering the repository carries away the maximum amount of uranium.

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