Abstract
The core transient behavior calculation code `EXCURS` for a Na-cooled oxide fuel fast reactor was modified for the application to a Na-cooled metal fuel fast reactor (LMR). The results of the core transient behavior calculated with the modified EXCURS were compared with those calculated by ANL for EBR-II and also compared with those by CRIEPI for 1000MWe-LMR. These calculations agreed quite well. The modified EXCURS, therefore, can be used for analysing the core transient behavior of LMR. In a design study of actinide burner reactors (ABR), the analysis of core transient behavior is important from the viewpoint of safety. The ULOF and UTOP analyses for a Na-cooled metal fuel ABR (M-ABR) were carried out using the modified EXCURS. The effect of heat conductivity of fuel and that of feedback reactivity coefficients on the core transient behavior were also evaluated. It is calculated that the maximum temperature of fuel is strongly affected by flowering reactivity coefficient, delayed neutron fraction and heat conductivity of fuel in this order. (author).
Okajima, Shigeaki;
Mukaiyama, Takehiko;
[1]
Gunji, Yasuyoshi
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Okajima, Shigeaki, Mukaiyama, Takehiko, and Gunji, Yasuyoshi.
A computer code for analysis of core transient behavior in a Na-cooled metal fuel fast reactor. Modification of the code EXCURS and sample calculation.
Japan: N. p.,
1992.
Web.
Okajima, Shigeaki, Mukaiyama, Takehiko, & Gunji, Yasuyoshi.
A computer code for analysis of core transient behavior in a Na-cooled metal fuel fast reactor. Modification of the code EXCURS and sample calculation.
Japan.
Okajima, Shigeaki, Mukaiyama, Takehiko, and Gunji, Yasuyoshi.
1992.
"A computer code for analysis of core transient behavior in a Na-cooled metal fuel fast reactor. Modification of the code EXCURS and sample calculation."
Japan.
@misc{etde_10149625,
title = {A computer code for analysis of core transient behavior in a Na-cooled metal fuel fast reactor. Modification of the code EXCURS and sample calculation}
author = {Okajima, Shigeaki, Mukaiyama, Takehiko, and Gunji, Yasuyoshi}
abstractNote = {The core transient behavior calculation code `EXCURS` for a Na-cooled oxide fuel fast reactor was modified for the application to a Na-cooled metal fuel fast reactor (LMR). The results of the core transient behavior calculated with the modified EXCURS were compared with those calculated by ANL for EBR-II and also compared with those by CRIEPI for 1000MWe-LMR. These calculations agreed quite well. The modified EXCURS, therefore, can be used for analysing the core transient behavior of LMR. In a design study of actinide burner reactors (ABR), the analysis of core transient behavior is important from the viewpoint of safety. The ULOF and UTOP analyses for a Na-cooled metal fuel ABR (M-ABR) were carried out using the modified EXCURS. The effect of heat conductivity of fuel and that of feedback reactivity coefficients on the core transient behavior were also evaluated. It is calculated that the maximum temperature of fuel is strongly affected by flowering reactivity coefficient, delayed neutron fraction and heat conductivity of fuel in this order. (author).}
place = {Japan}
year = {1992}
month = {Mar}
}
title = {A computer code for analysis of core transient behavior in a Na-cooled metal fuel fast reactor. Modification of the code EXCURS and sample calculation}
author = {Okajima, Shigeaki, Mukaiyama, Takehiko, and Gunji, Yasuyoshi}
abstractNote = {The core transient behavior calculation code `EXCURS` for a Na-cooled oxide fuel fast reactor was modified for the application to a Na-cooled metal fuel fast reactor (LMR). The results of the core transient behavior calculated with the modified EXCURS were compared with those calculated by ANL for EBR-II and also compared with those by CRIEPI for 1000MWe-LMR. These calculations agreed quite well. The modified EXCURS, therefore, can be used for analysing the core transient behavior of LMR. In a design study of actinide burner reactors (ABR), the analysis of core transient behavior is important from the viewpoint of safety. The ULOF and UTOP analyses for a Na-cooled metal fuel ABR (M-ABR) were carried out using the modified EXCURS. The effect of heat conductivity of fuel and that of feedback reactivity coefficients on the core transient behavior were also evaluated. It is calculated that the maximum temperature of fuel is strongly affected by flowering reactivity coefficient, delayed neutron fraction and heat conductivity of fuel in this order. (author).}
place = {Japan}
year = {1992}
month = {Mar}
}