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Severe accident tests and development of domestic severe accident system codes

Abstract

According to lessons learned from Fukushima-Daiichi NPS accidents, the safety evaluation will be started based on the NRA's New Safety Standards. In parallel with this movement, reinforcement of Severe Accident (SA) Measures and Accident Managements (AMs) has been undertaken and establishments of relevant regulations and standards are recognized as urgent subjects. Strengthening responses against nuclear plant hazards, as well as realistic protection measures and their standardization is also recognized as urgent subjects. Furthermore, decommissioning of Fukushima-Daiichi Unit1 through Unit4 is promoted diligently. Taking into account JNES's mission with regard to these SA Measures, AMs and decommissioning, movement of improving SA evaluation methodologies inside and outside Japan, and prioritization of subjects based on analyses of sequences of Fukushima-Daiichi NPS accidents, three viewpoints was extracted. These viewpoints were substantiated as the following three groups of R and D subjects: (1) Obtaining near term experimental subjects: Containment venting, Seawater injection, Iodine behaviors. (2) Obtaining mid and long experimental subjects: Fuel damage behavior at early phase of core degradation, Core melting and debris formation. (3) Development of a macroscopic level SA code for plant system behaviors and a mechanistic level code for core melting and debris formation. (author)
Publication Date:
Aug 15, 2013
Product Type:
Technical Report
Report Number:
JNES-RE-2013-0001
Resource Relation:
Other Information: 2 refs., 9 figs.; This record replaces 46062871; Related Information: In: Annual safety research report, JFY 2012| Japan Nuclear Energy Safety Organization, Tokyo (Japan)| 708 p.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCIDENT MANAGEMENT; COMPUTER CODES; CONTAINMENT; CORIUM; CRITICALITY; FUKUSHIMA-1 REACTOR; FUKUSHIMA-2 REACTOR; FUKUSHIMA-3 REACTOR; INJECTION; IODINE; MELTDOWN; MELTING; NUCLEAR POWER PLANTS; REGULATIONS; SAFETY ANALYSIS; SEAWATER; VENTS
OSTI ID:
22357696
Research Organizations:
Japan Nuclear Energy Safety Organization, Nuclear Energy System Safety Dept., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
TRN: JP1501610062871
Availability:
Available from the Internet at URL http://www.nsr.go.jp/archive/jnes/content/000125907.pdf
Submitting Site:
INIS
Size:
page(s) 359-368
Announcement Date:
Jul 20, 2015

Citation Formats

None. Severe accident tests and development of domestic severe accident system codes. Japan: N. p., 2013. Web.
None. Severe accident tests and development of domestic severe accident system codes. Japan.
None. 2013. "Severe accident tests and development of domestic severe accident system codes." Japan.
@misc{etde_22357696,
title = {Severe accident tests and development of domestic severe accident system codes}
author = {None}
abstractNote = {According to lessons learned from Fukushima-Daiichi NPS accidents, the safety evaluation will be started based on the NRA's New Safety Standards. In parallel with this movement, reinforcement of Severe Accident (SA) Measures and Accident Managements (AMs) has been undertaken and establishments of relevant regulations and standards are recognized as urgent subjects. Strengthening responses against nuclear plant hazards, as well as realistic protection measures and their standardization is also recognized as urgent subjects. Furthermore, decommissioning of Fukushima-Daiichi Unit1 through Unit4 is promoted diligently. Taking into account JNES's mission with regard to these SA Measures, AMs and decommissioning, movement of improving SA evaluation methodologies inside and outside Japan, and prioritization of subjects based on analyses of sequences of Fukushima-Daiichi NPS accidents, three viewpoints was extracted. These viewpoints were substantiated as the following three groups of R and D subjects: (1) Obtaining near term experimental subjects: Containment venting, Seawater injection, Iodine behaviors. (2) Obtaining mid and long experimental subjects: Fuel damage behavior at early phase of core degradation, Core melting and debris formation. (3) Development of a macroscopic level SA code for plant system behaviors and a mechanistic level code for core melting and debris formation. (author)}
place = {Japan}
year = {2013}
month = {Aug}
}