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k_(eff)uncertainty quantification and analysis due to nuclear data during the full lifetime burnup calculation for a small-sized prismatic high temperature gas-cooled reactor

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nuclear Science and Techniques 2021年第11期32卷 105-118页

作者： Rong-Rui Yang Yuan Yuan Chen Hao Ji Ma Guang-Hao Liu Fundamental Science on nuclear Safety and Simulation Technology Laboratory College of Nuclear Science and TechnologyHarbin Engineering UniversityHarbin 150001China Department of Reactor Technology Beijing Institute of Nuclear EngineeringChina Nuclear Power Engineering Co.LtdBeijing 100089China

To benefit from recent advances in modeling and computational algorithms,as well as the availability of new covariance data,sensitivity and uncertainty analyses are needed to quantify the impact of uncertain sources on the design parameters of small prismatic high-temperature gascooled reactors(HTGRs).In particular,the contribution of nuclear data to the k_(eff)uncertainty is an important part of the uncertainty analysis of small-sized HTGR physical *** this study,a small-sized HTGR designed by China nuclear Power Engineering Co.,*** selected for k_(eff)uncertainty analysis during full lifetime burnup *** of the cold zero power(CZP)condition and full lifetime burnup process were constructed using the Reactor Monte Carlo Code RMC for neutron transport calculation,depletion calculation,and sensitivity and uncertainty *** the sensitivity analysis,the Contribution-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance Characterization(CLUTCH)method was applied to obtain sensitive information,and the "sandwich" method was used to quantify the k_(eff)*** also compared the k_(eff)uncertainties to other typical *** results show that ^(235)U is the largest contributor to k_(eff)uncertainty for both the CZP and depletion conditions,while the contribution of ^(239)Pu is not very significant because of the design of low discharge *** is worth noting that the radioactive capture reaction of ^(28)Si significantly contributes to the k_(eff)uncertainty owing to its specific fuel ***,the k_(eff)uncertainty during the full lifetime depletion process was relatively stable,only increasing by 1.12%owing to the low discharge burnup design of small-sized *** numerical results are beneficial for neutronics design and core parameters optimization in further uncertainty propagation and quantification study for small-sized HTGR.

关键词： Small-sized HTGR SU analysis nuclear data Burnup

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维普期刊数据库

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Iterative Bayesian Monte Carlo for nuclear data evaluation

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nuclear Science and Techniques 2022年第4期33卷 105-135页

作者： Erwin Alhassan Dimitri Rochman Alexander Vasiliev Mathieu Hursin Arjan JKoning Hakim Ferroukhi Laboratory for Reactor Physics and Thermal-Hydraulics Paul Scherrer Institute5232 VilligenSwitzerland Division Large Research Facilities(GFA) Paul Scherrer InstituteVilligenSwitzerland Ecole Polytechnique Federale de Lausanne LausanneSwitzerland nuclear data Section International Atomic Energy Commission(IAEA)ViennaAustria Division of Applied nuclear Physics Department of Physics and AstronomyUppsala UniversityUppsalaSweden

In this work,we explore the use of an iterative Bayesian Monte Carlo(iBMC)method for nuclear data evaluation within a TALYS Evaluated nuclear data Library(TENDL)*** goal is to probe the model and parameter space of the TALYS code system to find the optimal model and parameter sets that reproduces selected experimental *** method involves the simultaneous variation of many nuclear reaction models as well as their parameters included in the TALYS ***‘best’model set with its parameter set was obtained by comparing model calculations with selected experimental *** experimental data types were used:(1)reaction cross sections,(2)residual production cross sections,and(3)the elastic angular *** improve our fit to experimental data,we update our‘best’parameter set—the file that maximizes the likelihood function—in an iterative *** was determined by monitoring the evolution of the maximum likelihood estimate(MLE)values and was considered reached when the relative change in the MLE for the last two iterations was within 5%.Once the final‘best’file is identified,we infer parameter uncertainties and covariance information to this file by varying model parameters around this *** this way,we ensured that the parameter distributions are centered on our *** proposed method was applied to the evaluation of p+^(59)Co between 1 and 100 ***,the adjusted files were compared with experimental data from the EXFOR database as well as with evaluations from the TENDL-2019,JENDL/He-2007 and JENDL-4.0/HE nuclear data libraries.

关键词： Iterative Bayesian Monte Carlo(iBMC) nuclear reaction models Model parameters Adjustments Bayesian calibration nuclear data TALYS

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Neutron nuclear data evaluation of actinide nuclei for CENDL-3.1

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Chinese Physics C 2012年第9期36卷 823-826页

作者：陈国长曹文田于保生唐国有施兆民陶曦 Laboratory of Science and Technology on nuclear data China Institute of Atomic EnergyBeijing 102413China School of Physics&State Key Laboratory of nuclear Physics and Technology Peking UniversityBeijing 100871China

New evaluations for several actinide nuclei of the third version of Chinese Evaluated nuclear data Library for Neutron Reaction data （CENDL-3.1） have been completed and released. The evaluation is for all neutron induced reactions with uranium, neptunium, plutonium and americium in the mass range A-232-241, 236 239, 236-246 and 240-244, respectively, and cover the incident neutron energy up to 20 MeV. In the present evaluation, much more effort was devoted to improving the reliability of the evaluated nuclear data for available new measured data, especially scarce or absent experimental data. A general description for the evaluation of several actinides＇ data is presented.

关键词： actinide nuclear data evaluation CENDL neutron

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Advantages and disadvantages of nuclear reactions used in reactors or cyclotrons,in addition to a theoretical study based on photodisintegration on natural indium for^(111)Ag production

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nuclear Science and Techniques 2022年第2期33卷 1-13页

作者： Khaled M.El-Azony Nader M.A.Mohamed Dalal A.Aloraini Radioactive Isotopes and Generators Department Hot Labs.CenterEgyptian Atomic Energy AuthorityP.O.Box 13759CairoEgypt Reactors Department Egyptian Atomic Energy AuthorityP.O.Box 13759CairoEgypt Physics Department College of SciencePrincess Nourah Bint Abdulrahman UniversityRiyadhKingdom of Saudi Arabia

Production routes were recorded on available reactions for^(111)Ag production from nuclear reactors or cyclotrons using a natural palladium target based on^(110)Pd(n,γ)and^(110)pd(d,n)reactions,respectively.^(nat)Cd(γ,x)based on^(110)Cd(γ,p)has also been studied as a prospective reaction for the production of^(111)***,these nuclear reactions are difficult to utilize because,in some cases,they reduce the specific activity of^(111)*** is a consequence of the stable silver isotopes produced in high *** isotopes include^(107,109)Ag and,in other cases,the high impurity of silver radioisotopes,such as^(110)m,^(106)m,^(105)Ag,that are produced during parallel nuclear *** to a scarcity of data regarding the(γ,α)reaction,the gamma reaction on natural indium for^(111)Ag production based on the^(115)In(γ,α)reaction was *** ^(nat)In(γ,α)reaction satisfies the criteria as a possible reaction to produce^(111)Ag with a sufficient yield and purity as consequence of the high^(115)In(95.7%)abundance as an enriched form and a relatively soft background caused by the parallel nuclear reactions.

关键词： Silver-111 nuclear data Natural cadmium Natural palladium Natural indium

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Updated and revised neutron reaction data for ^(233)U

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Chinese Physics C 2013年第7期37卷 27-32页

作者：于保生陈国长张华曹文田唐国有陶曦 Laboratory of Science and Technology on nuclear data China Institute of Atomic Energy School of Physics & State Key Laboratory of nuclear Physics and Technology Peking University

A complete set of n＋233U neutron reaction data from 10-6 eV-20 MeV is updated and revised based on the evaluated experimental data and the feedback information of various benchmark tests, The main revised quantities are nubars, cross sections as well as angular distributions, etc. The benchmark tests indicate that the present evaluated data achieve very promising results.

关键词： 233U nuclear data evaluation CENDL neutron

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Study on intermediate energy nucleon-nuclei reaction

Study on intermediate energy nucleon-nuclei reaction

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第十三届全国核结构研讨会暨第九次全国“核结构与量子力学”专题讨论会

作者： Li Ou (College of Physics and Technology,Guangxi Normal University,Guilin,541004,P.R.China)

The spallation reaction is studied widely not only because of its widely application but also because it is a useful theory method for nuclear physics *** nuclear data,including mass,charge, isotope distributions and double differential cross sections of nucleon,for proton-induced spallation reactions at intermediate energy on various targets are analyzed by the improved quantum molecular dynamics model (ImQMD05) merged with the generalized evaporation model(GEM2) and GEMINI *** calculation results are found to be in good agreement with experimental data with the adjusted parameters using in GEM2 and *** on the same model,the effects of the density dependence of the symmetry energy and the thickness of neutron skin on proton(neutron) induced reactions on Sn isotopes are *** investigation shows that the target size dependence of the reaction cross sections for proton induced reactions on Sn isotopes is sensitive to the density dependence of the symmetry energy and less sensitive to the thickness of neutron skin of target nuclei,but that for neutron induced reactions on Sn isotopes is less sensitive to the density dependence of the symmetry energy and sensitive to the thickness of neutron skin of target nucleus.

关键词： spallation reaction nuclear data symmetry energy neutron skin

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