First Experiments at the CIGMA Facility for Investigations of LWR Containment Thermal Hydraulics

2016 ◽  
Author(s):  
Yasuteru Sibamoto ◽  
Satoshi Abe ◽  
Masahiro Ishigaki ◽  
Taisuke Yonomoto
Keyword(s):  
Nuclear Power ◽  
Steam Injection ◽  
Light Water Reactor ◽  
Thermal Hydraulics ◽  
Japan Atomic Energy Agency ◽  
Power Station ◽  
Experimental Conditions ◽  
Energy Agency ◽  
Severe Accidents ◽  
External Cooling

There has been an extensive reorientation of the light water reactor (LWR) research in Japan since the Fukushima Dai-ichi nuclear power station (NPS) accident, which focuses on severe accidents and accident managements. The Japan Atomic Energy Agency (JAEA) initiated the ROSA-SA project in 2013 for the purpose of studying thermal hydraulics relevant to over-temperature containment damage, hydrogen risk, and fission product transport. For this purpose, the JAEA newly constructed the Containment InteGral Measurement Apparatus (CIGMA) in 2015 for the experiments addressing containment responses, separate effects, and accident managements. Recently, we successfully conducted first experiments using CIGMA to characterize the facility under typical experimental conditions investigating basic phenomena such as buildup of pressure by steam injection, containment cooling and depressurization by internal or external cooling, and density stratified layer mixing by impinging jet. This paper provides an overview of the research programs, the brief description of the facility specification and the outcomes obtained from the first experiments.

Performance degradation of candidate accident-tolerant cladding under corrosive environment

2017 ◽  
Vol 35 (3) ◽  
pp. 129-140 ◽  
Author(s):  
Fumihisa Nagase ◽  
Kan Sakamoto ◽  
Shinichiro Yamashita
Keyword(s):  
Nuclear Power ◽  
Fission Products ◽  
Zirconium Alloys ◽  
Performance Degradation ◽  
Lessons Learned ◽  
Light Water Reactor ◽  
Fuel Cladding ◽  
Power Station ◽  
Light Water ◽  
Fukushima Daiichi

AbstractLight-water reactor (LWR) fuel cladding shall retain the performance as the barrier for nuclear fuel materials and fission products in high-pressure and high-temperature coolant under irradiation conditions for long periods. The cladding also has to withstand temperature increase and severe loading under accidental conditions. As lessons learned from the accident at the Fukushima Daiichi nuclear power station, advanced cladding materials are being developed to enhance accident tolerance compared to conventional zirconium alloys. The present paper reviews the progress of the development and summarizes the subjects to be solved for enhanced accident-tolerant fuel cladding, focusing on performance degradation under various corrosive environmental conditions that should be considered in designing the LWR fuel.

II. Specialized Agencies

1969 ◽  
Vol 23 (4) ◽  
pp. 990-996
Keyword(s):  
United Kingdom ◽  
Nuclear Power Station ◽  
International Atomic Energy Agency ◽  
Nuclear Power ◽  
Atomic Energy ◽  
Power Station ◽  
Energy Agency ◽  
New Members ◽  
The United Kingdom ◽  
Board Of Governors

The report of the Board of Governors of the International Atomic Energy Agency (IAEA) to the tenth General Conference of the Agency covered the period from July 1, 1965, to June 30, 1966. During that time the Agency’s membership increased from 92 to 96; the new members were Jamaica, Jordan, Kenya, and Panama.The period under review was marked by further growth in IAEA’s safeguards activities. In June 1966 the Agency provisionally approved special procedures for safeguarding reprocessing plants. During the year the number of safeguards agreements approved by the Board increased from 24 to 29. One new agreement covered a major nuclear power station in the United Kingdom.

Methodology for integral analysis of ATWS for Kuosheng nuclear power station

Kerntechnik ◽  
2021 ◽  
Vol 86 (2) ◽  
pp. 116-127
Author(s):  
H.-C. Chien ◽  
K.-H. Jsu ◽  
A.-S. Lin ◽  
H.-T. Lin ◽  
C. T. Lin
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Primary System ◽  
Power Station ◽  
Integral Analysis ◽  
Emergency Procedures ◽  
Analysis Methodology ◽  
System Integrity ◽  
Severe Accidents

Abstract An integral analysis methodology for BWR ATWS has been developed. The method covers main scopes about ATWS events, including radiological consequence, primary system integrity, fuel integrity, containment integrity, and long-term shutdown and cooling capability. The primary techniques about this methodology were described herein. The methodology has been applied on Kuosheng nuclear power station to show the applicability. Under this framework, some suggestions were proposed for further development of this methodology. This methodology can give a way to evaluate safety of BWR plants confidently. Further, it can be a tool for developing emergency procedures about severe accidents, or exploring strategies and checking their effectiveness.

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