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

Wade, H.M.

United States. Department of Energy. Office of Scientific and Technical Information.

关键词: Viability;    Wastes;    Pwr Type Reactors;    11 Nuclear Fuel Cycle And Fuel Materials;    Nuclear Fuels;   

DOI  :  10.2172/860280
RP-ID  :  CAL-UDC-ME-000001 REV 00
RP-ID  :  NA
RP-ID  :  860280

美国|英语

来源: UNT Digital Library

【 摘 要 】

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.