scholarly journals Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

2014 ◽  
Author(s):  
Tai Asayama ◽  
Yugi Nagae ◽  
Takashi Wakai ◽  
Kazuyuki Tsukimori ◽  
Masaki Morishita
Keyword(s):  
Life Cycle ◽  
Elevated Temperature ◽  
Fast Reactor ◽  
Structural Design ◽  
Reliability Assessment ◽  
Japan Society ◽  
Code System ◽  
Fast Reactors ◽  
Leak Before Break ◽  
Integrated Code

This paper describes the latest status on the development of elevated temperature materials and structural codes for Japanese sodium-cooled fast reactors (SFRs). Based on the extensive research and development activities in the last decades in Japan, two materials, 316FR and Modified 9Cr-1Mo steels were recently incorporated into the 2012 Edition of Fast Reactor Design and Construction Code of the Japan Society of Mechanical Engineers (JSME). Structural design methodologies are continuously being improved towards the next major revision planed in 2016 Edition where methodologies for a 60-year design of Japanese demonstration fast reactor will be provided. Codes and guidelines for fitness-for-service, leak-before-break evaluation and reliability assessment are concurrently being developed utilizing the System Based Code concept aiming at establishing an integrated code system that encompasses a life cycle of SFRs. Paper published with permission.

Development of Structural Codes for JSFR Based on the System Based Code Concept

2014 ◽  
Author(s):  
Tai Asayama ◽  
Takashi Wakai ◽  
Masanori Ando ◽  
Satoshi Okajima ◽  
Yuji Nagae ◽  
...  
Keyword(s):  
Research And Development ◽  
Fast Reactor ◽  
Structural Reliability ◽  
Reliability Evaluation ◽  
Current Status ◽  
Japan Society ◽  
Ongoing Research ◽  
Reactor Types ◽  
Conceptual Study ◽  
Leak Before Break

This paper overviews the current status of the ongoing research and development as well as activities for codification of structural codes for the Japan Sodium Cooled Fast Reactor (JSFR), the demonstration fast reactor which is in the phase of conceptual study. Not only the design and construction code which has been published and updated on a regular basis, codes on welding, fitness-for-service, leak-before-break evaluation as well as the guidelines for structural reliability evaluation are being developed. The basic strategy for the development is to fully take advantage of the favorable technical characteristics associated with sodium-cooled fast reactors; the codes will be developed based on the System Based Code concept, a concept that materializes code rules that are most suitable to the reactor types they are applied to. The above mentioned set of codes are planned to be published from the Japan Society of Mechanical Engineers in 2016.

Prospects for fast reactors

1987 ◽  
Vol 92 (1-2) ◽  
pp. 57-71
Author(s):  
C. W. Blumfield
Keyword(s):  
Fast Reactor ◽  
High Energy ◽  
High Energy Density ◽  
Fast Reactors ◽  
Advantages And Disadvantages ◽  
Reactor Technology ◽  
European Collaboration ◽  
Fast Reactor Fuel ◽  
Fuel Reprocessing ◽  
Planned Activities

SynopsisThe background to recent major advances in the construction and operation of fast reactors is outlined with particular reference to the Dounreay Prototype Fast Reactor. The advantages and disadvantages of sodium as a coolant of the high energy density assembly are discussed and an account given of the consequences of a leak and the precautions taken against this eventuality. Attention is drawn to the safety aspects of the system. The economics of the plans for fuel reprocessing are explained and an account given of the progress in the fabrication of fast reactor fuel pins. Finally the environmental impact of present and planned activities on the Dounreay site is presented in the context of participation in the European Collaboration on Fast Reactor Technology and attention drawn to the importance of the planning inquiry in progress at Dounreay.

Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system

2018 ◽  
Vol 121 ◽  
pp. 324-334
Author(s):  
Xianan Du ◽  
Youqi Zheng ◽  
Liangzhi Cao ◽  
Hongchun Wu
Keyword(s):  
Fast Reactor ◽  
Transient Analysis ◽  
Code System
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