Review of waste package verification tests. Semiannual report, October 1984-March 1985
- ed.
The potential of WAPPA, a second-generation waste package system code, to meet the needs of the regulatory community is analyzed. The analysis includes an indepth review of WAPPA`s individual process models and a review of WAPPA`s operation. It is concluded that the code is of limited use to the NRC in the present form. Recommendations for future improvement, usage, and implementation of the code are given. This report also describes the results of a testing program undertaken to determine the chemical environment that will be present near a high-level waste package emplaced in a basalt repository. For this purpose, low carbon 1020 steel (a current BWIP reference container material), synthetic basaltic groundwater and a mixture of bentonite and basalt were exposed, in an autoclave, to expected conditions some period after repository sealing (150{sup 0}C, {approx_equal}10.4 MPa). Parameters measured include changes in gas pressure with time and gas composition, variation in dissolved oxygen (DO), pH and certain ionic concentrations of water in the packing material across an imposed thermal gradient, mineralogic alteration of the basalt/bentonite mixture, and carbon steel corrosion behavior. A second testing program was also initiated to check the likelihood of stress corrosion cracking of austenitic stainless steels and Incoloy 825 which are being considered for use as waste container materials in the tuff repository program. 82 refs., 70 figs., 27 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 60581
- Report Number(s):
- NUREG/CR--3091-Vol.6; BNL-NUREG--51630-Vol.6; ON: TI85017037
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
ARGON
BASALT
CARBON STEELS
CHEMICAL COMPOSITION
COMPUTERIZED SIMULATION
CORROSION
CORROSIVE EFFECTS
DISSOLVED GASES
EXPERIMENTAL DATA
GAS ANALYSIS
GROUND WATER
HIGH PRESSURE
HIGH-LEVEL RADIOACTIVE WASTES
INCOLOY 825
METALLOGRAPHY
METHANE
MICROSTRUCTURE
OXYGEN
PH VALUE
PHYSICAL RADIATION EFFECTS
RADIOACTIVE WASTE DISPOSAL
STAINLESS STEEL-304L
STAINLESS STEEL-316L
STAINLESS STEEL-321
STEAM
STRESS CORROSION
TEMPERATURE RANGE 0400-1000 K
TUFF
Yucca Mountain Project