Published 1986 | Version v1
Report Metadata-only

Analysis of spent fuel behavior in dry storage cask demonstrations in the West Germany

Creators

  • 1. Deuteche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH, West Germany

Description

Full scale dry storage cask demonstrations with irradiated PWR and BWR fuel elements have been conducted since 1979 and support the technical bases for dry storage of spent fuel. These tests have involved app. 3.000 fuel rods, with maximum cladding temperatures ranging from 250 to 430 0C. There is no evidence that any rods exposed to inert gases have failed during extended dry storage. Dry storage under cask conditions with maximum insertion temperatures in the range of 400 0C does not expect to cause a significant creep deformation above 1%, cladding oxidation and conditions that induce SCC or flaw propagation

Additional details

Publishing Information

Imprint Title
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 1
Journal Page Range
p. S.253-S.262.
Report number
CONF-860417--Vol.1

Conference

Title
3. international symposium/workshop on irradiated fuel storage.
Dates
8-10 Apr 1986.
Place
Seattle, WA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18023297
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CASKS; CREEP; DRY STORAGE; FUEL INTEGRITY; FUEL RODS; HEAT TRANSFER; OXIDATION; PERFORMANCE TESTING; PWR TYPE REACTORS
Descriptors DEC
CHEMICAL REACTIONS; CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; STORAGE; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS