scholarly journals Nuclear Data and Measurement Series - a method to construct covariance files in ENDF/B format for criticality safety applications.

10.2172/12069 ◽  
1999 ◽  
Author(s):  
D.G. Naberejnev ◽  
D.L. Smith
Keyword(s):  
Nuclear Data ◽  
Measurement Series ◽  
Safety Applications ◽  
Criticality Safety

scholarly journals Contributions to integral nuclear data in ICSBEP and IRPhEP since ND2016

2020 ◽  
Vol 239 ◽  
pp. 18007
Author(s):  
John Darrell Bess ◽  
Tatiana Ivanova ◽  
J. Blair Briggs
Keyword(s):  
Spectral Characteristics ◽  
Nuclear Data ◽  
Nuclear Facilities ◽  
Reactor Physics ◽  
Benchmark Experiment ◽  
Reactivity Coefficients ◽  
Physics Experiment ◽  
Safety Applications ◽  
Evaluation Project ◽  
Criticality Safety

The contributions to the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) was last presented to the international nuclear data community at ND2016. Since ND2016, integral benchmark data that are available for nuclear data testing has continued to increase. The 2018 edition of the International Handbook of Evaluated Criti-cality Safety Benchmark Experiments (ICSBEP Handbook) now contains 574 evaluations with benchmark specifications for 4,916 critical, near-critical, or subcritical configurations, 45 criticality alarm placement/shielding configuration with multiple dose points apiece, and 215 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. The 2018 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook) contains data from 159 different experimental series that were performed at 54 different nuclear facilities. Currently 156 of the 159 evaluations are published as approved benchmarks with the remaining three evaluations published as drafts. Measurements found in the IRPhEP Handbook include criticality, buckling and extrapolation length, spectral characteristics, reactivity effects, reactivity coefficients, kinetics, reaction-rate distributions, power distributions, isotopic compositions, and/or other miscellaneous types of measurements for various types of reactor systems. Additional benchmark evaluations will be included in the 2019 editions of these handbooks. These handbooks continue to represent the standard for neutronics benchmark experiment evaluation.

scholarly journals Nuclear Data Uncertainty Quantification in Criticality Safety Evaluations for Spent Nuclear Fuel Geological Disposal

2021 ◽  
Vol 11 (14) ◽  
pp. 6499
Author(s):  
Matthias Frankl ◽  
Mathieu Hursin ◽  
Dimitri Rochman ◽  
Alexander Vasiliev ◽  
Hakim Ferroukhi
Keyword(s):  
Uncertainty Quantification ◽  
Nuclear Fuel ◽  
Evaluation Method ◽  
Spent Nuclear Fuel ◽  
Nuclear Data ◽  
Data Uncertainty ◽  
Evaluation Methodology ◽  
Geological Disposal ◽  
Fuel Assemblies ◽  
Criticality Safety

Presently, a criticality safety evaluation methodology for the final geological disposal of Swiss spent nuclear fuel is under development at the Paul Scherrer Institute in collaboration with the Swiss National Technical Competence Centre in the field of deep geological disposal of radioactive waste. This method in essence pursues a best estimate plus uncertainty approach and includes burnup credit. Burnup credit is applied by means of a computational scheme called BUCSS-R (Burnup Credit System for the Swiss Reactors–Repository case) which is complemented by the quantification of uncertainties from various sources. BUCSS-R consists in depletion, decay and criticality calculations with CASMO5, SERPENT2 and MCNP6, respectively, determining the keff eigenvalues of the disposal canister loaded with the Swiss spent nuclear fuel assemblies. However, the depletion calculation in the first and the criticality calculation in the third step, in particular, are subject to uncertainties in the nuclear data input. In previous studies, the effects of these nuclear data-related uncertainties on obtained keff values, stemming from each of the two steps, have been quantified independently. Both contributions to the overall uncertainty in the calculated keff values have, therefore, been considered as fully correlated leading to an overly conservative estimation of total uncertainties. This study presents a consistent approach eliminating the need to assume and take into account unrealistically strong correlations in the keff results. The nuclear data uncertainty quantification for both depletion and criticality calculation is now performed at once using one and the same set of perturbation factors for uncertainty propagation through the corresponding calculation steps of the evaluation method. The present results reveal the overestimation of nuclear data-related uncertainties by the previous approach, in particular for spent nuclear fuel with a high burn-up, and underline the importance of consistent nuclear data uncertainty quantification methods. However, only canister loadings with UO2 fuel assemblies are considered, not offering insights into potentially different trends in nuclear data-related uncertainties for mixed oxide fuel assemblies.

scholarly journals Neutron nuclear data measurements for criticality safety

2017 ◽  
Vol 146 ◽  
pp. 11020
Author(s):  
Klaus Guber ◽  
Carlos Paradela ◽  
Jan Heyse ◽  
Stefan Kopecky ◽  
Peter Schillebeeckx ◽  
...  
Keyword(s):  
Nuclear Data ◽  
Criticality Safety

scholarly journals Verification of MCNP6.1 and MCNP6.1.1 for Criticality Safety Applications

2014 ◽  
Author(s):  
Forrest B. Brown ◽  
Brian C. Kiedrowski ◽  
Jeffrey S. Bull
Keyword(s):  
Safety Applications ◽  
Criticality Safety

On the options for incorporating nuclear data uncertainties in criticality safety assessments for LWR fuel

2018 ◽  
Vol 116 ◽  
pp. 57-68 ◽  
Author(s):  
A. Vasiliev ◽  
D. Rochman ◽  
M. Pecchia ◽  
H. Ferroukhi
Keyword(s):  
Nuclear Data ◽  
Safety Assessments ◽  
Criticality Safety

Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization

2014 ◽  
Vol 118 ◽  
pp. 341-345 ◽  
Author(s):  
M.L. Williams ◽  
G. Ilas ◽  
W.J. Marshall ◽  
B.T. Rearden
Keyword(s):  
Nuclear Data ◽  
Spent Fuel ◽  
Fuel Characterization ◽  
Criticality Safety
Sign in / Sign up

Export Citation Format

Share Document