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).
Ishihara, Masahiro;
Iyoku, Tatsuo;
Sato, Sadao;
Shiozawa, Shusaku;
[1]
Toyota, Junji
- Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
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}
}
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}
}