Summary of WIPP Room B heater test brine and backfill material data
Abstract
Simulated DHLW (Defense High Level Waste) package performance tests were carried out at the WIPP (Waste Isolation Pilot Plant) by emplacing a number of waste canisters containing electrical heaters into the floor of the mine. Peak temperatures were about 130{degrees}C, and the tests ran for three years. During this time, an unanticipated large amount of water was collected from heater hole BO42. A study was, therefore, undertaken to determine if this fluid was derived from normal weep brines. This was accomplished by comparing the amount of salt deposited by the dried weep brines with the volume of condensed steam collected during the test. Documenting the post-test condition of the various backfills was the other objective of this report. In spite of being exposed to acidic vapors, the bentonite-sand backfill retained its mineralogic integrity. However, the bentonite-sand backfill compacted between the canister and the wall only achieved a density that was about three quarters that of a pore-free material. The bentonite backfill also showed evidence of hair-line cracks through which steam had left the vicinity of the canister. In contrast, compacted crushed salt backfill exhibited no evidence of through-going cracks and was compacted to better than 99% of that of puremore »
- Authors:
- Publication Date:
- Research Org.:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Org.:
- USDOE; USDOE, Washington, DC (United States)
- OSTI Identifier:
- 5498076
- Report Number(s):
- SAND-90-0626
ON: DE91016871
- DOE Contract Number:
- AC04-76DP00789
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; BACKFILLING; PERFORMANCE TESTING; CONTAINERS; BENTONITE; BRINES; HEATERS; HIGH-LEVEL RADIOACTIVE WASTES; HYDROLYSIS; MAGNESIUM; PH VALUE; SALTS; SAND; TEMPERATURE DEPENDENCE; WIPP; ALKALINE EARTH METALS; CHEMICAL REACTIONS; CLAYS; DECOMPOSITION; ELEMENTS; FUNCTIONAL MODELS; LYSIS; MATERIALS; METALS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; PILOT PLANTS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTES; SOLVOLYSIS; TESTING; UNDERGROUND FACILITIES; US DOE; US ORGANIZATIONS; WASTES; 052002* - Nuclear Fuels- Waste Disposal & Storage
Citation Formats
Krumhansl, J L, Stein, C L, Jarrell, G D, and Kimball, K M. Summary of WIPP Room B heater test brine and backfill material data. United States: N. p., 1991.
Web.
Krumhansl, J L, Stein, C L, Jarrell, G D, & Kimball, K M. Summary of WIPP Room B heater test brine and backfill material data. United States.
Krumhansl, J L, Stein, C L, Jarrell, G D, and Kimball, K M. 1991.
"Summary of WIPP Room B heater test brine and backfill material data". United States.
@article{osti_5498076,
title = {Summary of WIPP Room B heater test brine and backfill material data},
author = {Krumhansl, J L and Stein, C L and Jarrell, G D and Kimball, K M},
abstractNote = {Simulated DHLW (Defense High Level Waste) package performance tests were carried out at the WIPP (Waste Isolation Pilot Plant) by emplacing a number of waste canisters containing electrical heaters into the floor of the mine. Peak temperatures were about 130{degrees}C, and the tests ran for three years. During this time, an unanticipated large amount of water was collected from heater hole BO42. A study was, therefore, undertaken to determine if this fluid was derived from normal weep brines. This was accomplished by comparing the amount of salt deposited by the dried weep brines with the volume of condensed steam collected during the test. Documenting the post-test condition of the various backfills was the other objective of this report. In spite of being exposed to acidic vapors, the bentonite-sand backfill retained its mineralogic integrity. However, the bentonite-sand backfill compacted between the canister and the wall only achieved a density that was about three quarters that of a pore-free material. The bentonite backfill also showed evidence of hair-line cracks through which steam had left the vicinity of the canister. In contrast, compacted crushed salt backfill exhibited no evidence of through-going cracks and was compacted to better than 99% of that of pure nonporous sodium chloride. Thus, the seal provided by a crushed salt backfill appears to be superior to that provided by bentonite. 13 refs., 6 tabs.},
doi = {},
url = {https://www.osti.gov/biblio/5498076},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jul 01 00:00:00 EDT 1991},
month = {Mon Jul 01 00:00:00 EDT 1991}
}