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

Technical Report:

Abstract

The graphite and carbon materials used for the core support graphite components of High Temperature Engineering Test Reactor (HTTR) are nuclear grade fine-grained isotropic graphite (IG-110), nuclear grade medium-grained near-isotropic graphite (PGX) and coarse-grained carbon (ASR-ORB). The material data on properties such as tensile strength, compressive strength, Young`s modulus, thermal expansion etc. of these graphites and carbon have been acquired up to now. From these obtained data the design data were stipulated by the graphite structural design code of core support graphite components of HTTR in order to design the core support graphite structures. This report explicates these design data for the core support graphite and carbon 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-91-154
Reference Number:
SCA: 220600; 210300; PA: JPN-91:012174; SN: 92000659208
Resource Relation:
Other Information: PBD: Oct 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; SUPPORTS; GRAPHITE; HTTR REACTOR; REACTOR CORES; REACTOR CORE RESTRAINTS; CARBON; TENSILE PROPERTIES; COMPRESSION STRENGTH; STRESSES; STRAINS; OXIDATION; HEAT TRANSFER; TEMPERATURE DEPENDENCE; EXPERIMENTAL DATA; 220600; 210300; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; POWER REACTORS, NONBREEDING, GRAPHITE MODERATED
OSTI ID:
10117053
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92768096; TRN: JP9112174
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
44 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 support 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 support 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 support components of High Temperature Engineering Test Reactor." Japan.
@misc{etde_10117053,
title = {An explication of design data of the graphite structural design code for core support components of High Temperature Engineering Test Reactor}
author = {Ishihara, Masahiro, Iyoku, Tatsuo, Sato, Sadao, Shiozawa, Shusaku, and Toyota, Junji}
abstractNote = {The graphite and carbon materials used for the core support graphite components of High Temperature Engineering Test Reactor (HTTR) are nuclear grade fine-grained isotropic graphite (IG-110), nuclear grade medium-grained near-isotropic graphite (PGX) and coarse-grained carbon (ASR-ORB). The material data on properties such as tensile strength, compressive strength, Young`s modulus, thermal expansion etc. of these graphites and carbon have been acquired up to now. From these obtained data the design data were stipulated by the graphite structural design code of core support graphite components of HTTR in order to design the core support graphite structures. This report explicates these design data for the core support graphite and carbon components of the HTTR. (author).}
place = {Japan}
year = {1991}
month = {Oct}
}