Abstract
The OECD Nuclear Energy Agency (NEA) has established a Task Group in the Committee on the Safety of Nuclear Installations (CSNI) to perform an analysis of Three Mile Island Unit 2 (TMI-2) accident as a standard problem to benchmark severe accident computer codes and to assess the capability of the codes. The TMI-2 Analysis Exercise was performed at the Japan Atomic Energy Research Institute (JAERI) using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage) - PM1/TMI code. The purpose of the analysis is to verify the capability of THALES-PM1/TMI code to describe accident progression in the actual plant. The present paper describes the final result of the TMI-2 Analysis Exercise performed at JAERI. (author).
Hashimoto, Kazuichiro;
Soda, Kunihisa
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Hashimoto, Kazuichiro, and Soda, Kunihisa.
Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code.
Japan: N. p.,
1991.
Web.
Hashimoto, Kazuichiro, & Soda, Kunihisa.
Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code.
Japan.
Hashimoto, Kazuichiro, and Soda, Kunihisa.
1991.
"Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code."
Japan.
@misc{etde_10117131,
title = {Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code}
author = {Hashimoto, Kazuichiro, and Soda, Kunihisa}
abstractNote = {The OECD Nuclear Energy Agency (NEA) has established a Task Group in the Committee on the Safety of Nuclear Installations (CSNI) to perform an analysis of Three Mile Island Unit 2 (TMI-2) accident as a standard problem to benchmark severe accident computer codes and to assess the capability of the codes. The TMI-2 Analysis Exercise was performed at the Japan Atomic Energy Research Institute (JAERI) using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage) - PM1/TMI code. The purpose of the analysis is to verify the capability of THALES-PM1/TMI code to describe accident progression in the actual plant. The present paper describes the final result of the TMI-2 Analysis Exercise performed at JAERI. (author).}
place = {Japan}
year = {1991}
month = {Oct}
}
title = {Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code}
author = {Hashimoto, Kazuichiro, and Soda, Kunihisa}
abstractNote = {The OECD Nuclear Energy Agency (NEA) has established a Task Group in the Committee on the Safety of Nuclear Installations (CSNI) to perform an analysis of Three Mile Island Unit 2 (TMI-2) accident as a standard problem to benchmark severe accident computer codes and to assess the capability of the codes. The TMI-2 Analysis Exercise was performed at the Japan Atomic Energy Research Institute (JAERI) using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage) - PM1/TMI code. The purpose of the analysis is to verify the capability of THALES-PM1/TMI code to describe accident progression in the actual plant. The present paper describes the final result of the TMI-2 Analysis Exercise performed at JAERI. (author).}
place = {Japan}
year = {1991}
month = {Oct}
}