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Examination on the safety criteria in safety assessment of fuel and core of the High Engineering Test Reactor (HTTR) under abnormal conditions

Technical Report:

Abstract

The safety criteria of the fuel and the core of the High Temperature Engineering Test Reactor (HTTR) was examined in order to assess the safety of the reactor at anticipated operational transients and at accidents. The safety criteria at the transients were decided as follows; the maximum fuel temperature shall not exceed 1600degC for the reactor core fuel, and it shall not exceed 2500degC for the fuel limit irradiation specimen, which is a fuel assembly with a graphite block and fuel elements for studying the fuel failure limit. On the other hand, the criteria for the accidents were decided so that (i) the fuel rod shall be held within the graphite block, and (ii) the support post and the post sheet shall maintain the strength enough to support the reactor core. Validity of the above criteria was ensured by the fuel behavior at representative abnormal events, namely, `abnormal events at the fuel limit irradiation test`, `rapid reactivity insertion events`, `air ingress accidents`, and `fuel assembly fall accidents`. (author).
Authors:
Hayashi, Kimio; Shindo, Masami; [1]  Shiozawa, Shusaku [2] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
  2. and others
Publication Date:
Sep 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-140
Reference Number:
SCA: 220900; 210300; 220600; PA: JPN-91:012157; SN: 92000659191
Resource Relation:
Other Information: PBD: Sep 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL INTEGRITY; SAFETY STANDARDS; REACTOR CORES; HTTR REACTOR; TRANSIENTS; REACTOR SAFETY; COATED FUEL PARTICLES; REACTIVITY; IRRADIATION; NSRR REACTOR; GRAPHITE; HELIUM; TEMPERATURE DEPENDENCE; FUEL ELEMENT FAILURE; 220900; 210300; 220600; POWER REACTORS, NONBREEDING, GRAPHITE MODERATED; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10117022
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92768079; TRN: JP9112157
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
69 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Hayashi, Kimio, Shindo, Masami, and Shiozawa, Shusaku. Examination on the safety criteria in safety assessment of fuel and core of the High Engineering Test Reactor (HTTR) under abnormal conditions. Japan: N. p., 1991. Web.
Hayashi, Kimio, Shindo, Masami, & Shiozawa, Shusaku. Examination on the safety criteria in safety assessment of fuel and core of the High Engineering Test Reactor (HTTR) under abnormal conditions. Japan.
Hayashi, Kimio, Shindo, Masami, and Shiozawa, Shusaku. 1991. "Examination on the safety criteria in safety assessment of fuel and core of the High Engineering Test Reactor (HTTR) under abnormal conditions." Japan.
@misc{etde_10117022,
title = {Examination on the safety criteria in safety assessment of fuel and core of the High Engineering Test Reactor (HTTR) under abnormal conditions}
author = {Hayashi, Kimio, Shindo, Masami, and Shiozawa, Shusaku}
abstractNote = {The safety criteria of the fuel and the core of the High Temperature Engineering Test Reactor (HTTR) was examined in order to assess the safety of the reactor at anticipated operational transients and at accidents. The safety criteria at the transients were decided as follows; the maximum fuel temperature shall not exceed 1600degC for the reactor core fuel, and it shall not exceed 2500degC for the fuel limit irradiation specimen, which is a fuel assembly with a graphite block and fuel elements for studying the fuel failure limit. On the other hand, the criteria for the accidents were decided so that (i) the fuel rod shall be held within the graphite block, and (ii) the support post and the post sheet shall maintain the strength enough to support the reactor core. Validity of the above criteria was ensured by the fuel behavior at representative abnormal events, namely, `abnormal events at the fuel limit irradiation test`, `rapid reactivity insertion events`, `air ingress accidents`, and `fuel assembly fall accidents`. (author).}
place = {Japan}
year = {1991}
month = {Sep}
}