Published January 25, 2000 | Version v1
Report Open

THERMAL HISTORY OF CLADDING IN A 21 PWR SNF WASTE PACKAGE LOADED WITH AVERAGE FUEL

Creators

Description

The purpose of this calculation is to evaluate a mid-assembly axial fuel cladding temperature profile of a 21 pressurized water reactor (PWR) spent nuclear fuel (SNF) waste package (WP) loaded with average fuel assemblies and emplaced in a monitored geologic repository. This calculation is intended to evaluate Viability Assessment (VA) and Enhanced Design Alternatives (EDA) II design configurations in support of performance assessment. This calculation was developed by Waste Package Operations (WPO) under Office of Civilian Radioactive Waste Management (OCRWM) procedure AP-3.12Q, Revision 0

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00860280; PURL: https://www.osti.gov/servlets/purl/860280-qxd6uY/

Files

37046821.pdf

Files (16.0 MB)

Name Size Download all
md5:ebc0a05bd0db4a5c074948ac9ce56e56
16.0 MB Preview Download

Additional details

Identifiers

URL
https://www.osti.gov/servlets/purl/860280-qxd6uY/;

Publishing Information

Imprint Pagination
111 p.
Report number
CAL-UDC-ME--000001

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
37046821
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
DESIGN; FUEL ASSEMBLIES; NUCLEAR FUELS; PERFORMANCE; PWR TYPE REACTORS; RADIOACTIVE WASTE MANAGEMENT; VIABILITY; WASTES
Descriptors DEC
ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MANAGEMENT; MATERIALS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Funding organization
US Department of Energy (United States)
Secondary number(s)
MOL--20000216.0105; DC-No--27604