Abstract
Fission product release analysis code, RACPAC (Fission Product Release Analysis Code from Fuel Particle in Accident Condition), was developed to calculate fractional release from the core during accident conditions of High Temperature Gas-cooled Reactor. RACPAC code has following features. (1) Fission product release fraction after the reactor scram is calculated based on the analytical solution with reduced diffusion coefficient. (2) The reduced diffusion coefficient for each nuclide is calculated from the (R/B) value, which is defined as release rate to birth rate of fission product. (3) The temperature transient after the accident can be taken into consideration in fractional release calculation with RACPAC. This paper describes calculation model of fission product release from fuel particle, calculation model of the reduced diffusion coefficient, users` manual and calculation examples. (author).
Sawa, Kazuhiro;
Tazawa, Yujiro;
[1]
Itakura, Hirofumi
- Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Citation Formats
Sawa, Kazuhiro, Tazawa, Yujiro, and Itakura, Hirofumi.
Fission product release analysis code during accident conditions of HTGR, RACPAC.
Japan: N. p.,
1991.
Web.
Sawa, Kazuhiro, Tazawa, Yujiro, & Itakura, Hirofumi.
Fission product release analysis code during accident conditions of HTGR, RACPAC.
Japan.
Sawa, Kazuhiro, Tazawa, Yujiro, and Itakura, Hirofumi.
1991.
"Fission product release analysis code during accident conditions of HTGR, RACPAC."
Japan.
@misc{etde_10109022,
title = {Fission product release analysis code during accident conditions of HTGR, RACPAC}
author = {Sawa, Kazuhiro, Tazawa, Yujiro, and Itakura, Hirofumi}
abstractNote = {Fission product release analysis code, RACPAC (Fission Product Release Analysis Code from Fuel Particle in Accident Condition), was developed to calculate fractional release from the core during accident conditions of High Temperature Gas-cooled Reactor. RACPAC code has following features. (1) Fission product release fraction after the reactor scram is calculated based on the analytical solution with reduced diffusion coefficient. (2) The reduced diffusion coefficient for each nuclide is calculated from the (R/B) value, which is defined as release rate to birth rate of fission product. (3) The temperature transient after the accident can be taken into consideration in fractional release calculation with RACPAC. This paper describes calculation model of fission product release from fuel particle, calculation model of the reduced diffusion coefficient, users` manual and calculation examples. (author).}
place = {Japan}
year = {1991}
month = {Aug}
}
title = {Fission product release analysis code during accident conditions of HTGR, RACPAC}
author = {Sawa, Kazuhiro, Tazawa, Yujiro, and Itakura, Hirofumi}
abstractNote = {Fission product release analysis code, RACPAC (Fission Product Release Analysis Code from Fuel Particle in Accident Condition), was developed to calculate fractional release from the core during accident conditions of High Temperature Gas-cooled Reactor. RACPAC code has following features. (1) Fission product release fraction after the reactor scram is calculated based on the analytical solution with reduced diffusion coefficient. (2) The reduced diffusion coefficient for each nuclide is calculated from the (R/B) value, which is defined as release rate to birth rate of fission product. (3) The temperature transient after the accident can be taken into consideration in fractional release calculation with RACPAC. This paper describes calculation model of fission product release from fuel particle, calculation model of the reduced diffusion coefficient, users` manual and calculation examples. (author).}
place = {Japan}
year = {1991}
month = {Aug}
}