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Rintala A, Valtavirta V, Leppänen J. Microscopic cross section calculation methodology in the Serpent 2 Monte Carlo code. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108603] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Jiménez-Carrascosa A, García-Herranz N, Krepel J, Margulis M, Baker U, Shwageraus E, Fridman E, Gregg R. Decay Heat Characterization for the European Sodium Fast Reactor. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2021. [DOI: 10.1115/1.4051798] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Abstract
In this work, a detailed assessment of the decay heat power for the commercial-size European sodium-cooled fast reactor (ESFR) at the end of its equilibrium cycle has been performed. The summation method has been used to compute very accurate spatial- and time-dependent decay heat by employing state-of-the-art coupled transport-depletion computational codes and nuclear data. This detailed map provides basic information for subsequent transient calculations of the ESFR. A comprehensive analysis of the decay heat has been carried out and interdependencies between decay heat and different parameters characterizing the core state prior to shutdowns, such as discharge burnup or type of fuel material, have been identified. That analysis has served as a basis to develop analytic functions to reconstruct the spatial-dependent decay heat power for the ESFR for cooling times within the first day after shutdown.
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Affiliation(s)
- Antonio Jiménez-Carrascosa
- Department of Energy Engineering, Universidad Politécnica de Madrid (UPM), José Gutiérrez Abascal, 2, Madrid 28006, Spain
| | - Nuria García-Herranz
- Department of Energy Engineering, Universidad Politécnica de Madrid (UPM), José Gutiérrez Abascal, 2, Madrid 28006, Spain
| | - Jiri Krepel
- Advanced Nuclear Systems Group, Paul Scherrer Institute (PSI), Villigen 5232, Switzerland
| | - Marat Margulis
- Nuclear Future Institute, Bangor University, Dean St., Bangor LL57 1 UT, UK
| | - Una Baker
- Department of Engineering, University of Cambridge (UCAM), Trumpington St., Cambridge CB2 1PZ, UK
| | - Eugene Shwageraus
- Department of Engineering, University of Cambridge (UCAM), Trumpington St., Cambridge CB2 1PZ, UK
| | - Emil Fridman
- Reactor Safety Group, Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Bautzner Landstraße 400, Dresden 01328, Germany
| | - Robert Gregg
- National Nuclear Laboratory (NNL), Chadwick House, Warrington WA3 6AE, UK
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Lognormal-Based Sampling for Fission Product Yields Uncertainty Propagation in Pebble-Bed HTGR. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2020. [DOI: 10.1155/2020/8014521] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
Abstract
Uncertainty analyses of fission product yields are indispensable in evaluating reactor burnup and decay heat calculation credibility. Compared with neutron cross section, there are fewer uncertainty analyses conducted and it has been a controversial topic by lack of properly estimated covariance matrix as well as adequate sampling method. Specifically, the conventional normal-based sampling method in sampling large uncertainty independent fission yields could inevitably generate nonphysical negative samples. Cutting off these samples would introduce bias into uncertainty results. Here, we evaluate thermal neutron-induced U-235 independent fission yields covariance matrix by the Bayesian updating method, and then we use lognormal-based sampling method to overcome the negative fission yields samples issue. Fission yields uncertainty contribution to effective multiplication factor and several fission products’ atomic densities at equilibrium core of pebble-bed HTGR are quantified and investigated. The results show that the lognormal-based sampling method could prevent generating negative yields samples and maintain the skewness of fission yields distribution. Compared with the zero cut-off normal-based sampling method, the lognormal-based sampling method evaluates the uncertainty of effective multiplication factor and atomic densities are larger. This implies that zero cut-off effect in the normal-based sampling method would underestimate the fission yields uncertainty contribution. Therefore, adopting the lognormal-based sampling method is crucial for providing reliable uncertainty analysis results in fission product yields uncertainty analysis.
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Kliem S, Grahn A, Bilodid Y, Höhne T. A realistic approach for the assessment of the consequences of heterogeneous boron dilution events in pressurized water reactors. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.04.038] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Applying the Serpent-DYN3D code sequence for the decay heat analysis of metallic fuel sodium fast reactor. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.11.020] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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