Published October 1987 | Version v1
Book

The analysis of transient criticality in wetted uranium dioxide systems and in fissile solutions

  • 1. UKAEA Safety and Reliability Directorate, Culcheth (UK)

Description

The use of uranium oxide powders and granules is common place in the nuclear industry and is manufactured and held in containers subject to stringent criticality revues. However inadvertent events such as the ingress of water might hypothetically cause criticality, and it is for the analysis of such events that a computer code POWDER has been developed. Similarly fissile solutions are used in factory processing and in experimental reactors, and interest in transient criticality in these solutions has continued over many years, with experiments both in the USA and in France. In order that understanding of the various physical mechanisms be obtained, and thus to be able to analyse hypothetical accidents, a computer code CRITEX has been written. This paper describes the physical mechanisms believed to be operating in the two situations, and outlines the methods used in the two codes. Some examples of the use of the codes POWDER and CRITEX are given, with comparison with experimental results. The work was partly funded by BNFL. (author)

Additional details

Publishing Information

Publisher
Dept. of Fuel Safety Res., Japan Atomic Energy Research Inst.
Imprint Place
Tokai, Ibaraki (Japan)
Imprint Title
ISCS'87
Imprint Pagination
503 p.
Journal Page Range
p. 440-444.

Conference

Title
International seminar on nuclear criticality safety.
Dates
19-23 Oct 1987.
Place
Tokyo (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
19051297
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
C CODES; CRITICALITY; FUEL SOLUTIONS; GRANULAR MATERIALS; P CODES; POWDERS; RADIATION ACCIDENTS; TRANSIENTS; URANIUM DIOXIDE; WETTABILITY
Descriptors DEC
ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; ENERGY SOURCES; FUELS; LIQUID FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; URANIUM COMPOUNDS; URANIUM OXIDES