Amanda M. Lewis, Denise Neudecker, Allan D. Carlson, Donald L. Smith, Ian Thompson, Anton Wallner, Devin P. Barry, Lee A. Bernstein, Robert C. Block, Stephen Croft, Yaron Danon, Manfred Drosg, Robert C. Haight, Michal W. Herman, Hye Young Lee, Naohiko Otuka, Henrik Sjöstrand, Vladimir Sobes
This paper provides a template of expected uncertainties and correlations for measurements of neutron-induced capture and charged-particle production cross sections. Measurements performed in-beam include total absorption spectroscopy, total energy detection, γ -ray spectroscopy, and direct charged-particle detection. Offline measurements include activation analysis and accelerator mass spectrometry. The information needed for proper use of the datasets in resonance region and high energy region evaluations is described, and recommended uncertainties are provided when specific values are not available for a dataset.
{"title":"Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables","authors":"Amanda M. Lewis, Denise Neudecker, Allan D. Carlson, Donald L. Smith, Ian Thompson, Anton Wallner, Devin P. Barry, Lee A. Bernstein, Robert C. Block, Stephen Croft, Yaron Danon, Manfred Drosg, Robert C. Haight, Michal W. Herman, Hye Young Lee, Naohiko Otuka, Henrik Sjöstrand, Vladimir Sobes","doi":"10.1051/epjn/2023015","DOIUrl":"https://doi.org/10.1051/epjn/2023015","url":null,"abstract":"This paper provides a template of expected uncertainties and correlations for measurements of neutron-induced capture and charged-particle production cross sections. Measurements performed in-beam include total absorption spectroscopy, total energy detection, γ -ray spectroscopy, and direct charged-particle detection. Offline measurements include activation analysis and accelerator mass spectrometry. The information needed for proper use of the datasets in resonance region and high energy region evaluations is described, and recommended uncertainties are provided when specific values are not available for a dataset.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135561284","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Denise Neudecker, A.M. Lewis, E.F. Matthews, J. Vanhoy, R.C. Haight, D.L. Smith, P. Talou, S. Croft, A.D. Carlson, B. Pierson, A. Wallner, Ali Al-Adili, Leslie Bernstein, R. Capote, Matthew J. Devlin, M. Drosg, D.L. Duke, S. Finch, M.W. Herman, K.J. Kelly, A. Koning, A.E. Lovell, Paola Marini, K. Montoya, G.P.A. Nobre, M. Paris, B. Pritychenko, H. Sjöstrand, L. Snyder, V. Sobes, A. Solders, Julien Taieb
The covariance committee of CSEWG (Cross Section Evaluation Working Group) established templates of expected measurement uncertainties for neutron-induced total, (n, γ ), neutron-induced charged-particle, and (n,xn) reaction cross sections as well as prompt fission neutron spectra, average prompt and total fission neutron multiplicities, and fission yields. Templates provide a list of what uncertainty sources are expected for each measurement type and observable, and suggest typical ranges of these uncertainties and correlations based on a survey of experimental data, associated literature, and feedback from experimenters. Information needed to faithfully include the experimental data in the nuclear-data evaluation process is also provided. These templates could assist (a) experimenters and EXFOR compilers in delivering more complete uncertainties and measurement information relevant for evaluations of new experimental data, and (b) evaluators in achieving a more comprehensive uncertainty quantification for evaluation purposes. This effort might ultimately lead to more realistic evaluated covariances for nuclear-data applications. In this topical issue, we cover the templates coming out of this CSEWG effort–typically, one observable per paper. This paper here prefaces this topical issue by introducing the concept and mathematical framework of templates, discussing potential use cases, and giving an example of how they can be applied (estimating missing experimental uncertainties of 235 U(n,f) average prompt fission neutron multiplicities), and their impact on nuclear-data evaluations.
{"title":"Templates of expected measurement uncertainties","authors":"Denise Neudecker, A.M. Lewis, E.F. Matthews, J. Vanhoy, R.C. Haight, D.L. Smith, P. Talou, S. Croft, A.D. Carlson, B. Pierson, A. Wallner, Ali Al-Adili, Leslie Bernstein, R. Capote, Matthew J. Devlin, M. Drosg, D.L. Duke, S. Finch, M.W. Herman, K.J. Kelly, A. Koning, A.E. Lovell, Paola Marini, K. Montoya, G.P.A. Nobre, M. Paris, B. Pritychenko, H. Sjöstrand, L. Snyder, V. Sobes, A. Solders, Julien Taieb","doi":"10.1051/epjn/2023014","DOIUrl":"https://doi.org/10.1051/epjn/2023014","url":null,"abstract":"The covariance committee of CSEWG (Cross Section Evaluation Working Group) established templates of expected measurement uncertainties for neutron-induced total, (n, γ ), neutron-induced charged-particle, and (n,xn) reaction cross sections as well as prompt fission neutron spectra, average prompt and total fission neutron multiplicities, and fission yields. Templates provide a list of what uncertainty sources are expected for each measurement type and observable, and suggest typical ranges of these uncertainties and correlations based on a survey of experimental data, associated literature, and feedback from experimenters. Information needed to faithfully include the experimental data in the nuclear-data evaluation process is also provided. These templates could assist (a) experimenters and EXFOR compilers in delivering more complete uncertainties and measurement information relevant for evaluations of new experimental data, and (b) evaluators in achieving a more comprehensive uncertainty quantification for evaluation purposes. This effort might ultimately lead to more realistic evaluated covariances for nuclear-data applications. In this topical issue, we cover the templates coming out of this CSEWG effort–typically, one observable per paper. This paper here prefaces this topical issue by introducing the concept and mathematical framework of templates, discussing potential use cases, and giving an example of how they can be applied (estimating missing experimental uncertainties of 235 U(n,f) average prompt fission neutron multiplicities), and their impact on nuclear-data evaluations.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"136079902","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Jeffrey R. Vanhoy, Robert C. Haight, Sally F. Hicks, Matthew Devlin, Denise Neudecker, Michal Herman, Arjan Koning, Keegan J. Kelly, Ian Thompson
A template is provided for evaluating experimental uncertainties for neutron elastic and inelastic scattering cross sections and γ -ray production cross sections from (n, xn) measurements at laboratories with monoenergetic or white neutron sources. A typical range of uncertainties is presented for experiments detecting the scattered neutrons or the resulting de-excitation γ rays based on a survey of available data and input from many experimentalists and theorists with extensive knowledge in the field. Models commonly used to evaluate the resulting cross-sections are also discussed. Suggestions are made regarding what experimental and uncertainty information is needed for data evaluations and should be included when reporting experimental (n, xn) cross sections. Uncertainty values and correlations are recommended if these values cannot be estimated for past data from the literature.
{"title":"Templates of expected measurement uncertainties for (n, xn) cross sections","authors":"Jeffrey R. Vanhoy, Robert C. Haight, Sally F. Hicks, Matthew Devlin, Denise Neudecker, Michal Herman, Arjan Koning, Keegan J. Kelly, Ian Thompson","doi":"10.1051/epjn/2023019","DOIUrl":"https://doi.org/10.1051/epjn/2023019","url":null,"abstract":"A template is provided for evaluating experimental uncertainties for neutron elastic and inelastic scattering cross sections and γ -ray production cross sections from (n, xn) measurements at laboratories with monoenergetic or white neutron sources. A typical range of uncertainties is presented for experiments detecting the scattered neutrons or the resulting de-excitation γ rays based on a survey of available data and input from many experimentalists and theorists with extensive knowledge in the field. Models commonly used to evaluate the resulting cross-sections are also discussed. Suggestions are made regarding what experimental and uncertainty information is needed for data evaluations and should be included when reporting experimental (n, xn) cross sections. Uncertainty values and correlations are recommended if these values cannot be estimated for past data from the literature.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135562240","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Denise Neudecker, A.D. Carlson, S. Croft, A.E Lovell, Matthew J. Devlin, Keegan J. Kelly, Julien Taieb, Paola Marini
In this paper, we provide templates of measurement uncertainty sources expected to appear for average prompt- and total-fission neutron multiplicities, $ overlinenu_p $ and $ overlinenu_t $ , for the following measurement types: absolute manganese-bath experiments for $ overlinenu_t $ , absolute and ratio liquid-scintillator measurements for $ overlinenu_p $ . These templates also suggest a typical range of these uncertainties and their correlations based on a survey of available experimental data, associated literature, and feedback from experimentalists. In addition, the information needed to faithfully include the associated experimental data into the nuclear-data evaluation process is provided.
{"title":"Templates of expected measurement uncertainties for average prompt and total fission neutron multiplicities","authors":"Denise Neudecker, A.D. Carlson, S. Croft, A.E Lovell, Matthew J. Devlin, Keegan J. Kelly, Julien Taieb, Paola Marini","doi":"10.1051/epjn/2023016","DOIUrl":"https://doi.org/10.1051/epjn/2023016","url":null,"abstract":"In this paper, we provide templates of measurement uncertainty sources expected to appear for average prompt- and total-fission neutron multiplicities, $ overlinenu_p $ and $ overlinenu_t $ , for the following measurement types: absolute manganese-bath experiments for $ overlinenu_t $ , absolute and ratio liquid-scintillator measurements for $ overlinenu_p $ . These templates also suggest a typical range of these uncertainties and their correlations based on a survey of available experimental data, associated literature, and feedback from experimentalists. In addition, the information needed to faithfully include the associated experimental data into the nuclear-data evaluation process is provided.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"136092826","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Amanda M. Lewis, Allan D. Carlson, Donald L. Smith, Devin P. Barry, Robert C. Block, Stephen Croft, Yaron Danon, Manfred Drosg, Michal W. Herman, Denise Neudecker, Naohiko Otuka, Henrik Sjöstrand, Vladimir Sobes
This paper provides a template of expected uncertainties and correlations for measurements of total neutron cross-section observables by transmission. Measurements with time-of-flight and mono-energetic neutron sources are covered. The information required for evaluations in the resonance region and high energy region is detailed, along with the template of uncertainties and correlations that can be used in the absence of other information.
{"title":"Templates of expected measurement uncertainties for total neutron cross-section observables","authors":"Amanda M. Lewis, Allan D. Carlson, Donald L. Smith, Devin P. Barry, Robert C. Block, Stephen Croft, Yaron Danon, Manfred Drosg, Michal W. Herman, Denise Neudecker, Naohiko Otuka, Henrik Sjöstrand, Vladimir Sobes","doi":"10.1051/epjn/2023018","DOIUrl":"https://doi.org/10.1051/epjn/2023018","url":null,"abstract":"This paper provides a template of expected uncertainties and correlations for measurements of total neutron cross-section observables by transmission. Measurements with time-of-flight and mono-energetic neutron sources are covered. The information required for evaluations in the resonance region and high energy region is detailed, along with the template of uncertainties and correlations that can be used in the absence of other information.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135609460","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
It is well known that a reactor is stable if the core reactivity decreases with the core power. This is the case for many types of reactors, including the PWR. However, this was not the case for the RBMK (Reaktor Bolshoy Moshchnosti Kanalniy) which could be unstable at low power. What does it mean precisely? By using a 2 × 2 system of non-linear ordinary differential equations we show that naturally (i.e. without using the control rods), with the same reactivity injection, if the initial power is lowered, then the final power may be higher, which is a rather unusual behaviour.
{"title":"Technical note: stable and unstable reactors","authors":"Bertrand Mercier, Volodymyr Borysenko","doi":"10.1051/epjn/2023017","DOIUrl":"https://doi.org/10.1051/epjn/2023017","url":null,"abstract":"It is well known that a reactor is stable if the core reactivity decreases with the core power. This is the case for many types of reactors, including the PWR. However, this was not the case for the RBMK (Reaktor Bolshoy Moshchnosti Kanalniy) which could be unstable at low power. What does it mean precisely? By using a 2 × 2 system of non-linear ordinary differential equations we show that naturally (i.e. without using the control rods), with the same reactivity injection, if the initial power is lowered, then the final power may be higher, which is a rather unusual behaviour.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135158170","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Denise Neudecker, Matthew J. Devlin, R.C. Haight, K.J. Kelly, Paola Marini, A.D. Carlson, Julien Taieb, M.C. White
In this paper, we provide templates of uncertainty sources expected to appear for three measurement types of prompt fission neutron spectra (PFNS): (1) shape measurements, (2) clean-ratio shape, that is the monitor PFNS are measured in nearly exactly the same surrounding as the PFNS of interest, and (3) indirect ratios, where the detector efficiency is backed out from PFNS monitor measurements. Information is also listed that is needed to faithfully include PFNS in nuclear data evaluations to guide experimenters on how to best report data and metadata for their measurements. These templates also suggest a typical range of pertinent uncertainty values and their correlations in case realistic uncertainties cannot be estimated from information on the measurement itself. The templates were based on a literature review, information found in EXFOR for 252 Cf, 235, 238 U, and 239 Pu PFNS, and enhanced by expertise from experimenters contributing to these PFNS templates.
{"title":"Templates of expected measurement uncertainties for prompt fission neutron spectra","authors":"Denise Neudecker, Matthew J. Devlin, R.C. Haight, K.J. Kelly, Paola Marini, A.D. Carlson, Julien Taieb, M.C. White","doi":"10.1051/epjn/2023013","DOIUrl":"https://doi.org/10.1051/epjn/2023013","url":null,"abstract":"In this paper, we provide templates of uncertainty sources expected to appear for three measurement types of prompt fission neutron spectra (PFNS): (1) shape measurements, (2) clean-ratio shape, that is the monitor PFNS are measured in nearly exactly the same surrounding as the PFNS of interest, and (3) indirect ratios, where the detector efficiency is backed out from PFNS monitor measurements. Information is also listed that is needed to faithfully include PFNS in nuclear data evaluations to guide experimenters on how to best report data and metadata for their measurements. These templates also suggest a typical range of pertinent uncertainty values and their correlations in case realistic uncertainties cannot be estimated from information on the measurement itself. The templates were based on a literature review, information found in EXFOR for 252 Cf, 235, 238 U, and 239 Pu PFNS, and enhanced by expertise from experimenters contributing to these PFNS templates.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135733766","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Maxime Paradis, X. Doligez, G. Marleau, M. Ernoult, N. Thiollière
Most fuel cycle simulation tools are based either on fixed recipes or assembly calculations for reactor modeling. Due to the high number of calculations and extensive computational power requirements, full-core computations are often seen as not viable for this purpose. However, this leads to additional hypotheses and modeling biases, thus limiting the realism of the resulting fuel cycle. For several applications, the current modeling method is sufficient, but precise calculations of discharged fuel composition may require further refinements. CLASS (Core Library for Advanced Simulation Scenarios) is a dynamic fuel cycle simulation code developed since 2012 with reactor models based on neural networks to produce nuclear data and physical quantities. Past work has shown a first coupling between CLASS and DONJON5 to quantify neural networks approach biases. This work assesses the applicability of 3D full-core diffusion calculations using the DONJON5 code coupled with nuclear scenario simulations involving a realistic PWR core at equilibrium cycle conditions. DONJON5 interpolates burnup dependent diffusion coefficients and cross sections generated beforehand by DRAGON5, a deterministic lattice calculation tool. Whereas previous studies considered only homogeneous reactors (i.e. homogeneous assembly in terms of composition and enrichment as well as homogeneous core), the present contribution focuses on the integration of full-core calculations in CLASS for fuel cycles involving a MOX/UO2 PWR core (i.e. 1/3 MOx–2/3 UOx). The DONJON5 model considered in this work describes a core with critical boron concentration at each time step partially loaded with MOx heterogeneous assemblies composed of three enrichments. In fuel cycle calculations, the main issue is to adapt, in the fabrication stage, the fresh fuel composition for the reactor with regards to the isotopic composition of the available stocks. This work presents a fuel loading model based on power peaking factors minimization that respects irradiation cycle length, 235U enrichment as well as Pu concentration and fissile quality, hence, ensuring a more uniform power distribution in the core.
大多数燃料循环模拟工具要么基于固定配方，要么基于反应堆建模的装配计算。由于大量的计算和广泛的计算能力需求，全核计算通常被认为是不可行的。然而，这会导致额外的假设和建模偏差，从而限制了最终燃料循环的真实性。对于一些应用，目前的建模方法是足够的，但排放燃料成分的精确计算可能需要进一步的改进。CLASS(高级模拟场景核心库)是自2012年以来开发的动态燃料循环模拟代码，基于神经网络的反应堆模型，用于生成核数据和物理量。过去的研究表明，CLASS和DONJON5之间的首次耦合可以量化神经网络方法的偏差。这项工作评估了3D全堆扩散计算的适用性，使用DONJON5代码结合核情景模拟，包括一个现实的压水堆堆芯在平衡循环条件下。DONJON5插值了由确定性晶格计算工具DRAGON5事先生成的与燃耗相关的扩散系数和截面。以前的研究只考虑了均质反应堆(即在组成和富集方面均质装配以及均质堆芯)，而目前的贡献侧重于在CLASS中集成涉及MOX/UO2压水堆堆芯(即1/3 MOX - 2/3 UOx)的燃料循环的全堆计算。本工作中考虑的DONJON5模型描述了在每个时间步具有临界硼浓度的核心，部分装载由三种富集组成的MOx非均相组件。在燃料循环计算中，主要问题是在制造阶段使反应堆的新鲜燃料成分与可用燃料的同位素组成相适应。本文提出了一种基于功率峰值因子最小化的燃料加载模型，该模型考虑了辐照周期长度、235U富集、Pu浓度和裂变质量，从而确保了堆芯中更均匀的功率分布。
{"title":"DONJON5/CLASS coupled simulations of MOX/UO2 heterogeneous PWR core","authors":"Maxime Paradis, X. Doligez, G. Marleau, M. Ernoult, N. Thiollière","doi":"10.1051/epjn/2021030","DOIUrl":"https://doi.org/10.1051/epjn/2021030","url":null,"abstract":"Most fuel cycle simulation tools are based either on fixed recipes or assembly calculations for reactor modeling. Due to the high number of calculations and extensive computational power requirements, full-core computations are often seen as not viable for this purpose. However, this leads to additional hypotheses and modeling biases, thus limiting the realism of the resulting fuel cycle. For several applications, the current modeling method is sufficient, but precise calculations of discharged fuel composition may require further refinements. CLASS (Core Library for Advanced Simulation Scenarios) is a dynamic fuel cycle simulation code developed since 2012 with reactor models based on neural networks to produce nuclear data and physical quantities. Past work has shown a first coupling between CLASS and DONJON5 to quantify neural networks approach biases. This work assesses the applicability of 3D full-core diffusion calculations using the DONJON5 code coupled with nuclear scenario simulations involving a realistic PWR core at equilibrium cycle conditions. DONJON5 interpolates burnup dependent diffusion coefficients and cross sections generated beforehand by DRAGON5, a deterministic lattice calculation tool. Whereas previous studies considered only homogeneous reactors (i.e. homogeneous assembly in terms of composition and enrichment as well as homogeneous core), the present contribution focuses on the integration of full-core calculations in CLASS for fuel cycles involving a MOX/UO2 PWR core (i.e. 1/3 MOx–2/3 UOx). The DONJON5 model considered in this work describes a core with critical boron concentration at each time step partially loaded with MOx heterogeneous assemblies composed of three enrichments. In fuel cycle calculations, the main issue is to adapt, in the fabrication stage, the fresh fuel composition for the reactor with regards to the isotopic composition of the available stocks. This work presents a fuel loading model based on power peaking factors minimization that respects irradiation cycle length, 235U enrichment as well as Pu concentration and fissile quality, hence, ensuring a more uniform power distribution in the core.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57827218","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
D. Rochman, A. Vasiliev, H. Ferroukhi, A. Koning, J. Sublet
In this paper, the impact of the thermal scattering data for H in H20 is estimated on criticality benchmarks, based on the variations of the CAB model parameters. The Total Monte Carlo method for uncertainty propagation is applied for 63 keff criticality cases, sensitive to H in H20. It is found that their impact is of a few tenth of pcm, up to 300 pcm maximum, and showing highly non-linear distributions. In a second step, an adjustment is proposed for these thermal scattering data, leading to a better agreement between calculated and experimental keff values, following an increase of scattering contribution. This work falls into the global approach of combining advanced theoretical modelling of nuclear data, followed by possible adjustment in order to improve the performances of a nuclear data library.
{"title":"Impact of H in H2O thermal scattering data on criticality calculation: uncertainty and adjustment","authors":"D. Rochman, A. Vasiliev, H. Ferroukhi, A. Koning, J. Sublet","doi":"10.1051/epjn/2021028","DOIUrl":"https://doi.org/10.1051/epjn/2021028","url":null,"abstract":"In this paper, the impact of the thermal scattering data for H in H20 is estimated on criticality benchmarks, based on the variations of the CAB model parameters. The Total Monte Carlo method for uncertainty propagation is applied for 63 keff criticality cases, sensitive to H in H20. It is found that their impact is of a few tenth of pcm, up to 300 pcm maximum, and showing highly non-linear distributions. In a second step, an adjustment is proposed for these thermal scattering data, leading to a better agreement between calculated and experimental keff values, following an increase of scattering contribution. This work falls into the global approach of combining advanced theoretical modelling of nuclear data, followed by possible adjustment in order to improve the performances of a nuclear data library.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57827212","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Heddy Barale, Camille Laguerre, Paul Sabatini, F. Courtin, K. Tirel, G. Martin
Scenario simulations are the main tool for studying the impact of a nuclear reactor fleet on the related fuel cycle facilities. This equilibrium preliminary study aims to present the functionalities of a new tool and to show the wide variety of reactors/cycles/strategies that can be studied in steady state conditions and validated with more details thanks to dynamic code. Different types of scenario simulation tools have been developed at CEA over the years, this study focuses on dynamic and equilibrium codes. Dynamic fuel cycle simulation code models the ingoing and outgoing material flow in all the facilities of a nuclear reactor fleet and their evolutions through the different nuclear processes over a given period of time. Equilibrium fuel cycle simulation code models advanced nuclear fuel cycles in equilibrium conditions, i.e. in conditions which stabilize selected nuclear inventories such as spent nuclear fuel constituents, plutonium or some minor actinides. The principle of this work is to analyze different nuclear reactors (PWR, AMR) and several fuel types (UOX, MOX, ERU, MIX) to simulate advanced nuclear fleet with partial and fully plutonium and uranium multi-recycling strategies at equilibrium. At this first stage, selected results are compared with COSI6 simulations in order to evaluate the precision of this new tool, showing a significant general agreement.
{"title":"A new tool for the simulation of different nuclear fleets at equilibrium","authors":"Heddy Barale, Camille Laguerre, Paul Sabatini, F. Courtin, K. Tirel, G. Martin","doi":"10.1051/epjn/2021025","DOIUrl":"https://doi.org/10.1051/epjn/2021025","url":null,"abstract":"Scenario simulations are the main tool for studying the impact of a nuclear reactor fleet on the related fuel cycle facilities. This equilibrium preliminary study aims to present the functionalities of a new tool and to show the wide variety of reactors/cycles/strategies that can be studied in steady state conditions and validated with more details thanks to dynamic code. Different types of scenario simulation tools have been developed at CEA over the years, this study focuses on dynamic and equilibrium codes. Dynamic fuel cycle simulation code models the ingoing and outgoing material flow in all the facilities of a nuclear reactor fleet and their evolutions through the different nuclear processes over a given period of time. Equilibrium fuel cycle simulation code models advanced nuclear fuel cycles in equilibrium conditions, i.e. in conditions which stabilize selected nuclear inventories such as spent nuclear fuel constituents, plutonium or some minor actinides. The principle of this work is to analyze different nuclear reactors (PWR, AMR) and several fuel types (UOX, MOX, ERU, MIX) to simulate advanced nuclear fleet with partial and fully plutonium and uranium multi-recycling strategies at equilibrium. At this first stage, selected results are compared with COSI6 simulations in order to evaluate the precision of this new tool, showing a significant general agreement.","PeriodicalId":44454,"journal":{"name":"EPJ Nuclear Sciences & Technologies","volume":null,"pages":null},"PeriodicalIF":0.5,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"57827159","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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