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Fission product release analysis code during accident conditions of HTGR, RACPAC

Technical Report:

Abstract

Fission product release analysis code, RACPAC (Fission Product Release Analysis Code from Fuel Particle in Accident Condition), was developed to calculate fractional release from the core during accident conditions of High Temperature Gas-cooled Reactor. RACPAC code has following features. (1) Fission product release fraction after the reactor scram is calculated based on the analytical solution with reduced diffusion coefficient. (2) The reduced diffusion coefficient for each nuclide is calculated from the (R/B) value, which is defined as release rate to birth rate of fission product. (3) The temperature transient after the accident can be taken into consideration in fractional release calculation with RACPAC. This paper describes calculation model of fission product release from fuel particle, calculation model of the reduced diffusion coefficient, users` manual and calculation examples. (author).
Authors:
Sawa, Kazuhiro; Tazawa, Yujiro; [1]  Itakura, Hirofumi
  1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Publication Date:
Aug 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-128
Reference Number:
SCA: 220900; 210300; 990200; PA: JPN-91:011150; SN: 92000630566
Resource Relation:
Other Information: PBD: Aug 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; FISSION PRODUCT RELEASE; R CODES; COATED FUEL PARTICLES; REACTOR ACCIDENTS; KRYPTON 88; TEMPERATURE DEPENDENCE; HTTR REACTOR; REACTOR CORES; IODINE 131; TIME DEPENDENCE; HIGH TEMPERATURE; VERY HIGH TEMPERATURE; 220900; 210300; 990200; REACTOR SAFETY; POWER REACTORS, NONBREEDING, GRAPHITE MODERATED; MATHEMATICS AND COMPUTERS
OSTI ID:
10109022
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92750959; TRN: JP9111150
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
39 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Sawa, Kazuhiro, Tazawa, Yujiro, and Itakura, Hirofumi. Fission product release analysis code during accident conditions of HTGR, RACPAC. Japan: N. p., 1991. Web.
Sawa, Kazuhiro, Tazawa, Yujiro, & Itakura, Hirofumi. Fission product release analysis code during accident conditions of HTGR, RACPAC. Japan.
Sawa, Kazuhiro, Tazawa, Yujiro, and Itakura, Hirofumi. 1991. "Fission product release analysis code during accident conditions of HTGR, RACPAC." Japan.
@misc{etde_10109022,
title = {Fission product release analysis code during accident conditions of HTGR, RACPAC}
author = {Sawa, Kazuhiro, Tazawa, Yujiro, and Itakura, Hirofumi}
abstractNote = {Fission product release analysis code, RACPAC (Fission Product Release Analysis Code from Fuel Particle in Accident Condition), was developed to calculate fractional release from the core during accident conditions of High Temperature Gas-cooled Reactor. RACPAC code has following features. (1) Fission product release fraction after the reactor scram is calculated based on the analytical solution with reduced diffusion coefficient. (2) The reduced diffusion coefficient for each nuclide is calculated from the (R/B) value, which is defined as release rate to birth rate of fission product. (3) The temperature transient after the accident can be taken into consideration in fractional release calculation with RACPAC. This paper describes calculation model of fission product release from fuel particle, calculation model of the reduced diffusion coefficient, users` manual and calculation examples. (author).}
place = {Japan}
year = {1991}
month = {Aug}
}