Applying the continuous-energy Monte Carlo calculation code, MVP3, to analysis of kinetic parameters measured for light-water moderated UO2 and MOX cores of the TCA and EOLE critical facilities

2020 ◽  
Vol 57 (7) ◽  
pp. 874-887 ◽  
Author(s):  
Toru Yamamoto ◽  
Daiki Iwahashi ◽  
Tomohiro Sakai
Keyword(s):  
Monte Carlo ◽  
Kinetic Parameters ◽  
Monte Carlo Calculation ◽  
Light Water ◽  
Continuous Energy ◽  
Critical Facilities ◽  
Calculation Code

scholarly journals DIAGNOSIS OF THE UNRESOLVED DOMAIN TREATMENT IN MONTE CARLO TRANSPORT CALCULATIONS THROUGH THE IDENTIFICATION AND MODELLING OF CRITICALITY SAFETY EXPERIMENTS

2021 ◽  
Vol 247 ◽  
pp. 10003
Author(s):  
N. García-Herranz ◽  
J. Rodríguez ◽  
A. Jiménez-Carrascosa ◽  
O. Cabellos
Keyword(s):  
Monte Carlo ◽  
Neutron Transport ◽  
Resonance Region ◽  
Nuclear Data ◽  
High Fidelity ◽  
Continuous Energy ◽  
Critical Facilities ◽  
Nuclear Systems ◽  
Monte Carlo Transport ◽  
Criticality Safety

Monte Carlo neutron transport codes can be used for high-fidelity predictions of the performance of nuclear systems. However, validation against experiments is required in order to establish the credibility in the results and identify the inaccuracies due to the used calculation scheme and associated databases. The International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP) contains criticality safety benchmarks derived from experiments that have been performed at various nuclear critical facilities around the world and are very valuable for validation purposes. The main objective of this work is the identification and modelling of experimental benchmarks included at ICSBEP in support of the validation of Monte Carlo neutron transport calculations when applied to fast systems, and in particular, KENO-VI and associated AMPX-formatted continuous-energy libraries from SCALE package. In such systems, the predicted k-eff values can be very sensitive to the treatment of nuclear data in the Unresolved Resonance Region (URR). Consequently, benchmarks with intermediate and fast spectra are identified and modelled with KENO-VI. Then, calculated results with and without probability tables in the URR are compared with each other in order to identify the most sensitive configurations to the URR. As a result of the proposed study, recommendations are given about the benchmarks that should be modelled and analysed to qualify the processed continuous-energy libraries before their use in Monte Carlo transport codes for practical fast reactor applications.

New Sampling Method in Continuous Energy Monte Carlo Calculation for Pebble Bed Reactors

1997 ◽  
Vol 34 (8) ◽  
pp. 734-744 ◽  
Author(s):  
Isao MURATA ◽  
Akito TAKAHASHI ◽  
Takamasa MORI ◽  
Masayuki NAKAGAWA
Keyword(s):  
Monte Carlo ◽  
Sampling Method ◽  
Monte Carlo Calculation ◽  
Pebble Bed ◽  
Pebble Bed Reactors ◽  
Continuous Energy
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