Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice

2018 ◽  
Vol 335 ◽  
pp. 432-440 ◽  
Author(s):  
Yunzhao Li ◽  
Bin Zhang ◽  
Qingming He ◽  
Dongyong Wang ◽  
Hongchun Wu ◽  
...  
Keyword(s):  
Code System ◽  
Fuel Management ◽  
Calculation Code

Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core

2018 ◽  
Vol 337 ◽  
pp. 279-290 ◽  
Author(s):  
Wen Yang ◽  
Hongchun Wu ◽  
Yunzhao Li ◽  
Jiewei Yang ◽  
Liangzhi Cao
Keyword(s):  
Code System ◽  
Fuel Management ◽  
Calculation Code

Application of Fine Depletion Calculation for LLFPs In-Core Transmutation Evaluation in PWRs

2012 ◽  
Author(s):  
Kun Liu ◽  
Hongchun Wu ◽  
Liangzhi Cao ◽  
Youqi Zheng ◽  
Changhui Wang
Keyword(s):  
Power Distribution ◽  
Critical Concentration ◽  
Verification And Validation ◽  
Code System ◽  
Fuel Management ◽  
Numerical Accuracy ◽  
Analysis And Evaluation ◽  
Evaluation Code ◽  
Flux Calculation ◽  
Numerical Performance

An in-core transmutation analysis and evaluation code, named CATE, considering in-core fine flux calculation and fine depletion process, is verified and validated in the present paper. Verification and Validation of implementations for the OECD/NEA PWR cell benchmark for actinides transmutation, IAEA PWR benchmark and infinite homogenized plate problem to confirm reliability and numerical accuracy for the code have been performed in presented paper. The numerical performance of the code system is demonstrated in the analyses of the in-core fuel management calculation. It is found that the present code system gives stability in prediction of critical concentration of boric solution and radial power distribution. Based on the verifications and validations, a preliminary LLFP transmutation pattern is calculated. Numerical results indicate that CATE can be used not only for the fuel management calculation, but also for in-core transmutation evaluation of PWR.

FMSR: A code system for in-core fuel management calculation of aqueous homogeneous solution reactor

2010 ◽  
Vol 240 (4) ◽  
pp. 763-770 ◽  
Author(s):  
Yunzhao Li ◽  
Hongchun Wu ◽  
Liangzhi Cao ◽  
Qichang Chen ◽  
Haoliang Lu ◽  
...  
Keyword(s):  
Homogeneous Solution ◽  
Code System ◽  
Fuel Management ◽  
Solution Reactor

Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment

2014 ◽  
Vol 63 ◽  
pp. 491-498 ◽  
Author(s):  
Meiyin Zheng ◽  
Wenxi Tian ◽  
Hongyang Wei ◽  
Dalin Zhang ◽  
Yingwei Wu ◽  
...  
Keyword(s):  
Accuracy Assessment ◽  
Code System ◽  
Calculation Code

Fuel management code system against experimental measurements of the CMRR reactor

2019 ◽  
Vol 130 ◽  
pp. 124-130 ◽  
Author(s):  
Guanbo Wang ◽  
Dazhi Qian ◽  
Jimin Ma ◽  
Rundong Li ◽  
Shu Yuan ◽  
...  
Keyword(s):  
Experimental Measurements ◽  
Code System ◽  
Fuel Management

Development of a nuclear-thermal coupled calculation code system

1995 ◽  
Vol 27 ◽  
pp. 269-274
Author(s):  
Shin-ichi Sugaya ◽  
Hiromitsu Kawasaki ◽  
Koubun Yamada ◽  
Yasushi Seki
Keyword(s):  
Code System ◽  
Coupled Calculation ◽  
Calculation Code

scholarly journals Development of a Calculation Code System for Evaluation of Deuteron Nuclear Data

2015 ◽  
Vol 71 ◽  
pp. 219-227 ◽  
Author(s):  
Shinsuke Nakayama ◽  
Shouhei Araki ◽  
Yukinobu Watanabe ◽  
Osamu Iwamoto ◽  
Tao Ye ◽  
...  
Keyword(s):  
Nuclear Data ◽  
Code System ◽  
Calculation Code
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