scholarly journals Development of a fuel depletion sensitivity calculation module for multi-cell problems in a deterministic reactor physics code system CBZ

2016 ◽  
Vol 96 ◽  
pp. 313-323 ◽  
Author(s):  
Go Chiba ◽  
Yosuke Kawamoto ◽  
Tadashi Narabayashi
Keyword(s):  
Code System ◽  
Reactor Physics ◽  
Sensitivity Calculation ◽  
Calculation Module

FAST Code System: Review of Recent Developments and Near-Future Plans

2009 ◽  
Author(s):  
Konstantin Mikityuk
Keyword(s):  
Comparative Analysis ◽  
Power Production ◽  
Code System ◽  
Reactor Physics ◽  
Recent Developments ◽  
Management Project ◽  
System Review ◽  
Paul Scherrer ◽  
Near Future ◽  
Future Plans

The FAST (Fast-spectrum Advanced Systems for power production and resource ManagemenT) project is an activity performed in the Laboratory for Reactor Physics and Systems Behaviour of Paul Scherrer Institut in the area of fast-spectrum reactor behaviour with an emphasis on the comparative analysis of Generation IV systems.

scholarly journals Uncertainty quantification works relevant to fission yields and decay data

2018 ◽  
Vol 4 ◽  
pp. 43
Author(s):  
Go Chiba ◽  
Shunsuke Nihira
Keyword(s):  
Perturbation Theory ◽  
Uncertainty Quantification ◽  
Nuclear Data ◽  
Code System ◽  
Reactor Physics ◽  
Delayed Neutrons ◽  
Decay Data ◽  
Decay Heat ◽  
Numerical Tools ◽  
Fission Yields

In the present paper, firstly, we review our previous works on uncertainty quantification (UQ) of reactor physics parameters. This consists of (1) development of numerical tools based on the depletion perturbation theory (DPT), (2) linearity of reactor physics parameters to nuclear data, (3) UQ of decay heat and its reduction, and (4) correlation between decay heat and β-delayed neutrons emission. Secondly, we show results of extensive calculations about UQ on decay heat with several different numerical conditions by the DPT-based capability of a reactor physics code system CBZ.

scholarly journals BURNUP SENSITIVITY CALCULATIONS WITH CBZ FOR LIGHT WATER REACTOR ASSEMBLY PROBLEMS

2021 ◽  
Vol 247 ◽  
pp. 15013
Author(s):  
Go Chiba
Keyword(s):  
Perturbation Theory ◽  
Nuclear Fuel ◽  
Nuclear Data ◽  
Light Water Reactor ◽  
Code System ◽  
Reactor Physics ◽  
Light Water ◽  
Water Reactor ◽  
Fuel Assemblies ◽  
Reactor Assembly

Sensitivities of k∞ and nuclides number densities during nuclear fuel burnup with respect to nuclear data are calculated with a reactor physics code system CBZ. Sensitivity calculations are carried out with the depletion perturbation theory applicable to nuclear fuel assemblies including burnable absorbers. Numerical results are presented both for BWR and PWR assemblies, and those demonstrate usefulness and effectiveness of burnup sensitivity calculation capabilities for LWR fuel assemblies.

Overview of Particle and Heavy Ion Transport Code System PHITS

2014 ◽  
Author(s):  
Tatsuhiko Sato ◽  
Koji Niita ◽  
Norihiro Matsuda ◽  
Shintaro Hashimoto ◽  
Yosuke Iwamoto ◽  
...  
Keyword(s):  
Ion Transport ◽  
Heavy Ion ◽  
Code System ◽  
Transport Code
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