Development and verification of fast reactor burnup calculation module FRBurner in code system CBZ

2021 ◽  
pp. 1-19
Author(s):  
Junshuang Fan ◽  
Go Chiba
Keyword(s):  
Fast Reactor ◽  
Code System ◽  
Calculation Module ◽  
Burnup Calculation

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

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.

FAST: An advanced code system for fast reactor transient analysis

2005 ◽  
Vol 32 (15) ◽  
pp. 1613-1631 ◽  
Author(s):  
Konstantin Mikityuk ◽  
Sandro Pelloni ◽  
Paul Coddington ◽  
Evaldas Bubelis ◽  
Rakesh Chawla
Keyword(s):  
Fast Reactor ◽  
Transient Analysis ◽  
Code System

Development of an Integrated Computer Code System for Analyzing Irradiation Behaviors of a Fast Reactor Fuel

2020 ◽  
pp. 1-10
Author(s):  
Tomoyuki Uwaba ◽  
Junichi Nemoto ◽  
Masahiro Ito ◽  
Ikuo Ishitani ◽  
Norihiro Doda ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Computer Code ◽  
Reactor Fuel ◽  
Code System ◽  
Fast Reactor Fuel

scholarly journals Effect of Np-239 on Fast Reactor Burnup Calculation

1978 ◽  
Vol 15 (2) ◽  
pp. 156-158
Author(s):  
Seiichi TAKEDA ◽  
Kazuyoshi MIKI
Keyword(s):  
Fast Reactor ◽  
Burnup Calculation

scholarly journals Verification of a two-step code system MCS/RAST-F to fast reactor core analysis

2021 ◽  
Author(s):  
Tuan Quoc Tran ◽  
Alexey Cherezov ◽  
Xianan Du ◽  
Deokjung Lee
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Core Analysis ◽  
Code System
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