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Computer simulation of fuel element performance

Abstract

The review presents reports made at the Conference on the Bahaviour and Production of Fuel for Water Reactors on March 13-17, 1979. Discussed at the Conference are the most developed and tested calculation models specially evolved to predict the behaviour of fuel elements of water reactors. The following five main aspects of the problem are discussed: general conceptions and programs; mechanical mock-ups and their applications; gas release, gap conductivity and fuel thermal conductivity; analysis of nonstationary processes; models of specific phenomena. The review briefly describes the physical principles of the following models and programs: the RESTR, providing calculation of the radii of zones of columnar and equiaxial grains as well as the radius of the internal cavity of the fuel core; programs for calculation of fuel-can interaction, based on the finite elements method; a model predicting the behaviour of the CANDU-PHW fuel elements in transient conditions. General results are presented of investigations of heat transfer through a can-fuel gap and thermal conductivity of UO/sub 2/ with regard for cracking and gas release of the fuel. Many programs already suit the accepted standards and are intensively tested at present.
Authors:
Publication Date:
Jan 01, 1979
Product Type:
Journal Article
Reference Number:
AIX-11-536047; EDB-80-117032
Resource Relation:
Journal Name: At. Tekh. Rubezhom; (USSR); Journal Volume: 8
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL ELEMENTS; PERFORMANCE; WATER COOLED REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; DECLADDING; FISSION PRODUCT RELEASE; FUEL CANS; FUEL-CLADDING INTERACTIONS; MATHEMATICAL MODELS; REVIEWS; THERMAL CONDUCTIVITY; TRANSIENTS; URANIUM DIOXIDE; ACTINIDE COMPOUNDS; CHALCOGENIDES; DOCUMENT TYPES; HEAD END PROCESSES; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES; 220300* - Nuclear Reactor Technology- Fuel Elements; 210400 - Power Reactors, Nonbreeding, Otherwise Moderated or Unmoderated
OSTI ID:
5135427
Country of Origin:
USSR
Language:
Russian
Other Identifying Numbers:
Journal ID: CODEN: ATRUA
Submitting Site:
INIS
Size:
Pages: 3-8
Announcement Date:
Jul 01, 1980

Citation Formats

Sukhanov, G I. Computer simulation of fuel element performance. USSR: N. p., 1979. Web.
Sukhanov, G I. Computer simulation of fuel element performance. USSR.
Sukhanov, G I. 1979. "Computer simulation of fuel element performance." USSR.
@misc{etde_5135427,
title = {Computer simulation of fuel element performance}
author = {Sukhanov, G I}
abstractNote = {The review presents reports made at the Conference on the Bahaviour and Production of Fuel for Water Reactors on March 13-17, 1979. Discussed at the Conference are the most developed and tested calculation models specially evolved to predict the behaviour of fuel elements of water reactors. The following five main aspects of the problem are discussed: general conceptions and programs; mechanical mock-ups and their applications; gas release, gap conductivity and fuel thermal conductivity; analysis of nonstationary processes; models of specific phenomena. The review briefly describes the physical principles of the following models and programs: the RESTR, providing calculation of the radii of zones of columnar and equiaxial grains as well as the radius of the internal cavity of the fuel core; programs for calculation of fuel-can interaction, based on the finite elements method; a model predicting the behaviour of the CANDU-PHW fuel elements in transient conditions. General results are presented of investigations of heat transfer through a can-fuel gap and thermal conductivity of UO/sub 2/ with regard for cracking and gas release of the fuel. Many programs already suit the accepted standards and are intensively tested at present.}
journal = []
volume = {8}
journal type = {AC}
place = {USSR}
year = {1979}
month = {Jan}
}