Published November 5, 1999 | Version v1
Report

Analysis of Dry Storage Temperature Limits for Zircaloy-Clad Spent Nuclear Fuel

Description

Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty years according to the Code of Federal Regulations. The most important variable that must be regulated by dry storage licensees in order to meet current safety standards is the temperature of the SNF. The two currently accepted models to define the maximum allowable initial storage temperature for SNF are based on the diffusion controlled cavity growth (DCCG) failure mechanism proposed by Raj and Ashby. These models may not give conservative temperature limits. Some have suggested using a strain-based failure model to predict the maximum allowable temperatures, but we have shown that this is not applicable to the SNF as long as DCCG is the assumed failure mechanism. Although the two accepted models are based on the same fundamental failure theory (DCCG), the researchers who developed the models made different assumptions, including selection of some of the most critical variables in the DCCG failure equation. These inconsistencies are discussed together with recommended modifications to the failure models based on more recent data

Availability note (English)

Available from PURL: https://www.osti.gov/servlets/purl/791267-CLzWNa/native/

Additional details

Publishing Information

Imprint Pagination
693 Kilobytes
Report number
UCRL-JC--131098

Conference

Title
Material Research Society Fall 1999 Meeting
Dates
29 Nov - 3 Dec 1999
Place
Boston, MA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
36056261
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DIFFUSION; DRY STORAGE; MODIFICATIONS; NUCLEAR FUELS; REGULATIONS; SAFETY STANDARDS; STORAGE
Descriptors DEC
ENERGY SOURCES; FUELS; LAWS; MATERIALS; REACTOR MATERIALS; STANDARDS; STORAGE

Optional Information

Contract/Grant/Project number
W--7405-Eng-48
Funding organization
USDOE Office of Defense Programs DP (United States)