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An explication of design data of the graphite structural design code for core components of High Temperature Engineering Test Reactor

Technical Report:

Abstract

The core graphite material used for the core graphite components such as fuel blocks, control rod blocks etc. of High Temperature Engineering Test Reactor (HTTR) is nuclear grade fine-grained isotropic graphite (IG-110). The material data on properties such as tensile strength, compressive strength, Young`s modulus, thermal expansion etc., including the effect of irradiation on these properties have been acquired up to now. From these obtained data the design data were stipulated by the graphite structural design code for core graphite components of HTTR in order to design the core graphite structures. This report explicates these design data for the core graphite components of the HTTR. (author).
Authors:
Ishihara, Masahiro; Iyoku, Tatsuo; Sato, Sadao; Shiozawa, Shusaku; [1]  Toyota, Junji
  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-91-153
Reference Number:
SCA: 360600; 220600; 210300; PA: JPN-91:012173; SN: 92000659207
Resource Relation:
Other Information: PBD: Oct 1991
Subject:
36 MATERIALS SCIENCE; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; GRAPHITE; HTTR REACTOR; BRITTLENESS; REACTOR CORES; PHYSICAL RADIATION EFFECTS; POISSON RATIO; CREEP; TEMPERATURE RANGE 1000-4000 K; THERMAL CONDUCTIVITY; OXIDATION; TENSILE PROPERTIES; YOUNG MODULUS; COMPRESSION STRENGTH; 360600; 220600; 210300; OTHER MATERIALS; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; POWER REACTORS, NONBREEDING, GRAPHITE MODERATED
OSTI ID:
10117386
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92768095; TRN: JP9112173
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
56 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Ishihara, Masahiro, Iyoku, Tatsuo, Sato, Sadao, Shiozawa, Shusaku, and Toyota, Junji. An explication of design data of the graphite structural design code for core components of High Temperature Engineering Test Reactor. Japan: N. p., 1991. Web.
Ishihara, Masahiro, Iyoku, Tatsuo, Sato, Sadao, Shiozawa, Shusaku, & Toyota, Junji. An explication of design data of the graphite structural design code for core components of High Temperature Engineering Test Reactor. Japan.
Ishihara, Masahiro, Iyoku, Tatsuo, Sato, Sadao, Shiozawa, Shusaku, and Toyota, Junji. 1991. "An explication of design data of the graphite structural design code for core components of High Temperature Engineering Test Reactor." Japan.
@misc{etde_10117386,
title = {An explication of design data of the graphite structural design code for core components of High Temperature Engineering Test Reactor}
author = {Ishihara, Masahiro, Iyoku, Tatsuo, Sato, Sadao, Shiozawa, Shusaku, and Toyota, Junji}
abstractNote = {The core graphite material used for the core graphite components such as fuel blocks, control rod blocks etc. of High Temperature Engineering Test Reactor (HTTR) is nuclear grade fine-grained isotropic graphite (IG-110). The material data on properties such as tensile strength, compressive strength, Young`s modulus, thermal expansion etc., including the effect of irradiation on these properties have been acquired up to now. From these obtained data the design data were stipulated by the graphite structural design code for core graphite components of HTTR in order to design the core graphite structures. This report explicates these design data for the core graphite components of the HTTR. (author).}
place = {Japan}
year = {1991}
month = {Oct}
}