Abstract
The core graphite components of the High Temperature Engineering Test Reactor (HTTR) show both the dimensional change (irradiation shrinkage) and creep behavior due to fast neutron irradiation under the temperature and the fast neutron irradiation conditions of the HTTR. Therefore, thermal/irradiation stress analytical code, VIENUS, which treats these graphite irradiation behavior, is to be employed in order to design the core components such as fuel block etc. of the HTTR. The VIENUS is a two dimensional finite element viscoelastic stress analytical code to take account of changes in mechanical properties, thermal strain, irradiation-induced dimensional change and creep in the fast neutron irradiation environment. Verification analyses were carried out in order to prove the validity of this code based on the irradiation tests of the 8th OGL-1 fuel assembly and the fuel element of the Peach Bottom reactor. This report describes the outline of the VIENUS code and its verification analyses. (author).
Iyoku, Tatsuo;
Ishihara, Masahiro;
Shiozawa, Shusaku;
[1]
Shirai, Hiroshi;
Minato, Kazuo
- Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Citation Formats
Iyoku, Tatsuo, Ishihara, Masahiro, Shiozawa, Shusaku, Shirai, Hiroshi, and Minato, Kazuo.
Verification of thermal-irradiation stress analytical code VIENUS of graphite block.
Japan: N. p.,
1992.
Web.
Iyoku, Tatsuo, Ishihara, Masahiro, Shiozawa, Shusaku, Shirai, Hiroshi, & Minato, Kazuo.
Verification of thermal-irradiation stress analytical code VIENUS of graphite block.
Japan.
Iyoku, Tatsuo, Ishihara, Masahiro, Shiozawa, Shusaku, Shirai, Hiroshi, and Minato, Kazuo.
1992.
"Verification of thermal-irradiation stress analytical code VIENUS of graphite block."
Japan.
@misc{etde_10149651,
title = {Verification of thermal-irradiation stress analytical code VIENUS of graphite block}
author = {Iyoku, Tatsuo, Ishihara, Masahiro, Shiozawa, Shusaku, Shirai, Hiroshi, and Minato, Kazuo}
abstractNote = {The core graphite components of the High Temperature Engineering Test Reactor (HTTR) show both the dimensional change (irradiation shrinkage) and creep behavior due to fast neutron irradiation under the temperature and the fast neutron irradiation conditions of the HTTR. Therefore, thermal/irradiation stress analytical code, VIENUS, which treats these graphite irradiation behavior, is to be employed in order to design the core components such as fuel block etc. of the HTTR. The VIENUS is a two dimensional finite element viscoelastic stress analytical code to take account of changes in mechanical properties, thermal strain, irradiation-induced dimensional change and creep in the fast neutron irradiation environment. Verification analyses were carried out in order to prove the validity of this code based on the irradiation tests of the 8th OGL-1 fuel assembly and the fuel element of the Peach Bottom reactor. This report describes the outline of the VIENUS code and its verification analyses. (author).}
place = {Japan}
year = {1992}
month = {Feb}
}
title = {Verification of thermal-irradiation stress analytical code VIENUS of graphite block}
author = {Iyoku, Tatsuo, Ishihara, Masahiro, Shiozawa, Shusaku, Shirai, Hiroshi, and Minato, Kazuo}
abstractNote = {The core graphite components of the High Temperature Engineering Test Reactor (HTTR) show both the dimensional change (irradiation shrinkage) and creep behavior due to fast neutron irradiation under the temperature and the fast neutron irradiation conditions of the HTTR. Therefore, thermal/irradiation stress analytical code, VIENUS, which treats these graphite irradiation behavior, is to be employed in order to design the core components such as fuel block etc. of the HTTR. The VIENUS is a two dimensional finite element viscoelastic stress analytical code to take account of changes in mechanical properties, thermal strain, irradiation-induced dimensional change and creep in the fast neutron irradiation environment. Verification analyses were carried out in order to prove the validity of this code based on the irradiation tests of the 8th OGL-1 fuel assembly and the fuel element of the Peach Bottom reactor. This report describes the outline of the VIENUS code and its verification analyses. (author).}
place = {Japan}
year = {1992}
month = {Feb}
}