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Siting evaluation of the High Temperature Engineering Test Reactor

Technical Report:

Abstract

Major and hypothetical accidents for siting evaluation of the High Temperature Engineering Test Reactor (HTTR) are evaluated. The purpose of the evaluation is to show the property of site location, i.e. a distance between the facilities and the public is kept enough so as to ensure the safety of the public even under the major and hypothetical accidents. The HTTR is a high temperature gas-cooled reactor adopting of coated fuel particles as fuel and graphite as moderator and core internal structures. Then the core temperature changes slowly and the instantaneous failure of coated fuel particles does not occur in accident conditions. Therefore, selection and analysis of siting evaluation events have been performed by methods different from LWRs`. A double-ended rupture of coaxial double pipe of the primary cooling system is selected as the major and hypothetical accident for siting evaluation of the HTTR. In order to evaluate radiation exposure during the accidents, time-dependent release of fission products which are contained in the core is assumed considering the above mentioned characteristics of the HTTR. This paper describes the selection of the events, analytical method are results of radiation exposure in the major and hypothetical accidents of the HTTR. (author).
Authors:
Sawa, Kazuhiro; Shiozawa, Shusaku; Tazawa, Yujiro; Iyoku, Tatsuo; Kitano, Kyoshiro; [1]  Shindo, Masami; Yamaguchi, Koshiro; Mikami, Hisashi
  1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Publication Date:
Oct 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-158
Reference Number:
SCA: 220501; 210300; 220600; 220900; PA: JPN-91:012176; SN: 92000659210
Resource Relation:
Other Information: PBD: Oct 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HTTR REACTOR; REACTOR SITES; PROBABILISTIC ESTIMATION; SITE SELECTION; FISSION PRODUCT RELEASE; RADIATION DOSES; TIME DEPENDENCE; PRIMARY COOLANT CIRCUITS; PIPES; RUPTURES; HYPOTHESIS; 220501; 210300; 220600; 220900; SITING; POWER REACTORS, NONBREEDING, GRAPHITE MODERATED; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; REACTOR SAFETY
OSTI ID:
10117057
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92768098; TRN: JP9112176
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
77 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Sawa, Kazuhiro, Shiozawa, Shusaku, Tazawa, Yujiro, Iyoku, Tatsuo, Kitano, Kyoshiro, Shindo, Masami, Yamaguchi, Koshiro, and Mikami, Hisashi. Siting evaluation of the High Temperature Engineering Test Reactor. Japan: N. p., 1991. Web.
Sawa, Kazuhiro, Shiozawa, Shusaku, Tazawa, Yujiro, Iyoku, Tatsuo, Kitano, Kyoshiro, Shindo, Masami, Yamaguchi, Koshiro, & Mikami, Hisashi. Siting evaluation of the High Temperature Engineering Test Reactor. Japan.
Sawa, Kazuhiro, Shiozawa, Shusaku, Tazawa, Yujiro, Iyoku, Tatsuo, Kitano, Kyoshiro, Shindo, Masami, Yamaguchi, Koshiro, and Mikami, Hisashi. 1991. "Siting evaluation of the High Temperature Engineering Test Reactor." Japan.
@misc{etde_10117057,
title = {Siting evaluation of the High Temperature Engineering Test Reactor}
author = {Sawa, Kazuhiro, Shiozawa, Shusaku, Tazawa, Yujiro, Iyoku, Tatsuo, Kitano, Kyoshiro, Shindo, Masami, Yamaguchi, Koshiro, and Mikami, Hisashi}
abstractNote = {Major and hypothetical accidents for siting evaluation of the High Temperature Engineering Test Reactor (HTTR) are evaluated. The purpose of the evaluation is to show the property of site location, i.e. a distance between the facilities and the public is kept enough so as to ensure the safety of the public even under the major and hypothetical accidents. The HTTR is a high temperature gas-cooled reactor adopting of coated fuel particles as fuel and graphite as moderator and core internal structures. Then the core temperature changes slowly and the instantaneous failure of coated fuel particles does not occur in accident conditions. Therefore, selection and analysis of siting evaluation events have been performed by methods different from LWRs`. A double-ended rupture of coaxial double pipe of the primary cooling system is selected as the major and hypothetical accident for siting evaluation of the HTTR. In order to evaluate radiation exposure during the accidents, time-dependent release of fission products which are contained in the core is assumed considering the above mentioned characteristics of the HTTR. This paper describes the selection of the events, analytical method are results of radiation exposure in the major and hypothetical accidents of the HTTR. (author).}
place = {Japan}
year = {1991}
month = {Oct}
}