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Thermal-hydraulic analysis of the Three Mile Island Unit 2 reactor accident with THALES code

Technical Report:

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).
Authors:
Hashimoto, Kazuichiro; Soda, Kunihisa [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Oct 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-193
Reference Number:
SCA: 210200; 570100; PA: JPN-91:012211; SN: 92000659245
Resource Relation:
Other Information: PBD: Oct 1991
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; THREE MILE ISLAND-2 REACTOR; LOSS OF COOLANT; T CODES; JAERI; HYDRAULICS; THERMODYNAMICS; BENCHMARKS; NEA; ECCS; HEAT TRANSFER; HYDROGEN; 210200; 570100; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; REAL ACCIDENTS
OSTI ID:
10117131
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE92768133; TRN: JP9112211
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
26 p.
Announcement Date:
Jun 30, 2005

Technical Report:

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}
}