Review of DOE waste package program. Subtask 1.1: National waste package program, April-September 1984. Volume 7; Thermal expansion and inferred permeability of climax quartz monzonite to 300{sup 0}C and 27.6 MPa

Technical Report · Thu Feb 28 23:00:00 EST 1985 · International Journal of Rock Mechanics and Mining Sciences and Geomechanics Abstracts

OSTI ID:59214

Soo, P ^[1]; Heard, H C

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1. ed.

The present effort is part of an ongoing task to review the national high-level waste package effort. It includes evaluations of reference waste form, container, and packing material components with respect to determining how they may contribute to the containment and controlled release of radionuclides after waste packages have been emplaced in salt, basalt, tuff, and granite repositories. In the current Biannual Report a review was carried out to determine the ability of spent fuel cladding to provide additional radionuclide containment capability should the container/overpack system fail prematurely.

• Research Organization: Brookhaven National Lab., Upton, NY (United States); Univ. of California, Livermore
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 59214
• Report Number(s): NUREG/CR--2482-Vol.7; BNL-NUREG--51494-Vol.7; ON: TI85008977
• Journal Information: International Journal of Rock Mechanics and Mining Sciences and Geomechanics Abstracts, Journal Name: International Journal of Rock Mechanics and Mining Sciences and Geomechanics Abstracts Journal Issue: 5 Vol. 17; ISSN IRMGBG
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
36 MATERIALS SCIENCE
BASALT
CONTAINERS
CONTAINMENT
CORROSION
EVALUATION
EXPERIMENTAL DATA
FAILURES
FUEL ELEMENT FAILURE
HIGH-LEVEL RADIOACTIVE WASTES
HYDRIDATION
PACKAGING
RADIOACTIVE WASTE DISPOSAL
SALT DEPOSITS
SPENT FUEL ELEMENTS
STAINLESS STEELS
TUFF
WASTE FORMS
Yucca Mountain Project
ZIRCALOY