Room closure response to gas generation and mechanical strength of different waste forms in a bedded salt repository

Conference · Sat May 01 00:00:00 EDT 1993

OSTI ID:10160310

Mendenhall, F T; Stone, C M

Finite element calculations of the porosity history of a nuclear waste disposal room in a bedded salt formation have been completed. The analyses include an elastic/secondary creep model for the host halite and a nonlinear consolidation model for the crushed salt backfill. Separate gas generation and constitutive models were used for three distinct waste forms, (1) unaltered defense related CH-TRU waste, (2) shredded and cemented CH-TRU waste, and (3) incinerated and vitrified CH-TRU waste. Solutions were determined for a 2000 year time period starting from the decommissioning of the repository. The resulting room porosities varied from roughly 55% to less than 10%.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 10160310
• Report Number(s): SAND-93-1135C; CONF-931108-1; ON: DE93013757; TRN: 93:019867
• Resource Relation: Conference: Fall meeting of the Materials Research Society (MRS),Boston, MA (United States),29 Nov - 3 Dec 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
WASTE FORMS
MECHANICAL PROPERTIES
SALT DEPOSITS
CREEP
ALPHA-BEARING WASTES
UNDERGROUND DISPOSAL
UNDERGROUND FACILITIES
POROSITY
GASES
FINITE ELEMENT METHOD
CEMENTS
WIPP
052002
360603
WASTE DISPOSAL AND STORAGE