A Bayesian Monte Carlo method for fission yield covariance information

Rochman, D.; Leray, O.; Vasiliev, A.; Ferroukhi, H.; Koning, A. J.; Fleming, Michael; Sublet, J.‐Ch.

doi:10.1016/j.anucene.2016.05.005

Cited by 29 publications

(21 citation statements)

References 29 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Such quantity was already calculated for nuclear data only in reference [24] and for the decay heat as a function of the cooling time in reference [10]. As an example, the correlation between the neutron source, gamma source and the decay heat for the PWR-2 (UO 2 ) is presented in Figure 13, for cooling time from 0.1 to 5 Â 10 5 years.…”

Section: Correlationmentioning

confidence: 99%

“…This is nevertheless not practical for uncertainty propagation and different methods are proposed to sample fission yields taking into account some degree of correlations. Examples can be found in references [7,10]. In the present work, the method developed in reference [11] is applied.…”

Section: Nuclear Datamentioning

confidence: 99%

“…Again, in the case of fission products, noticeable differences can be observed, to a large extent due to the fission yield library considered to perform the sampling. As already mentioned in references [10,7], there is a need of developing a reliable covariance matrix for fission yields in the context of SNF applications. The results based on evaluated or user-created fission yield covariance matrices still present strong variations for calculated quantities, indicating the necessity of additional efforts from the nuclear data evaluation community.…”

Section: Casementioning

confidence: 99%

See 2 more Smart Citations

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Rochman

Vasiliev

Dokhane

et al. 2018

EPJ Nuclear Sci. Technol.

View full text Add to dashboard Cite

Abstract. This paper presents a study of the impact of the nuclear data (cross sections, neutron emission and spectra) on different quantities for spent nuclear fuels (SNF) from Swiss power plants: activities, decay heat, neutron and gamma sources and isotopic vectors. Realistic irradiation histories are considered using validated core follow-up models based on CASMO and SIMULATE. Two Pressurized and one Boiling Water Reactors (PWR and BWR) are considered over a large number of operated cycles. All the assemblies at the end of the cycles are studied, being reloaded or finally discharged, allowing spanning over a large range of exposure (from 4 to 60 MWd/kgU for ≃9200 assembly-cycles). Both UO 2 and MOX fuels were used during the reactor cycles, with enrichments from 1.9 to 4.7% for the UO 2 and 2.2 to 5.8% Pu for the MOX. The SNF characteristics presented in this paper are calculated with the SNF code. The calculated uncertainties, based on the ENDF/B-VII.1 library are obtained using a simple Monte Carlo sampling method. It is demonstrated that the impact of nuclear data is relatively important (e.g. up to 17% for the decay heat), showing the necessity to consider them for safety analysis of the SNF handling and disposal.

show abstract

Section: Correlationmentioning

confidence: 99%

Section: Nuclear Datamentioning

confidence: 99%

Section: Casementioning

confidence: 99%

See 1 more Smart Citation

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Rochman

Vasiliev

Dokhane

et al. 2018

EPJ Nuclear Sci. Technol.

View full text Add to dashboard Cite

show abstract

“…Many simulation tools are capable of using such matrices to propagate nuclear data uncertainties on final quantities, with either perturbation theories [1][2][3][4][5][6], or Monte Carlo sampling [3,[7][8][9][10][11][12][13]. These results can for instance be used for the review procedure of new facilities, or during the safety assessment of new reactor core designs [14].…”

Section: Introductionmentioning

confidence: 99%

Correlationν̅_p − σ − χin the fast neutron range via integral information

Rochman

Bauge

Vasiliev

et al. 2017

EPJ Nuclear Sci. Technol.

View full text Add to dashboard Cite

Abstract. This paper presents a Bayesian approach based on integral experiments to create correlations which do not appear with differential data. Some quantities such as the fission cross section (s), neutron multiplicity (n p ), neutron spectra (x), etc. are usually neither modeled together nor measured in coincidence, thus there is no correlation matrices in evaluated nuclear data libraries. One can nevertheless use the information from integral experiments such as fast criticality-safety benchmarks to correlate such quantities for possible inclusion in nuclear data libraries. A simple Bayesian set of equations is presented with random nuclear data, similarly to the usual methods applied with differential data. An example for 239 Pu is proposed.

show abstract

“…The Bayesian Monte-Carlo (BMC) method applied to fission yields has been introduced in [1]. This method combines theoretical fission yields with a set of reference data.…”

Section: Introductionmentioning

confidence: 99%

Fission yield covariances for JEFF: A Bayesian Monte Carlo method

et al. 2017

View full text Add to dashboard Cite

Abstract. The JEFF library does not contain fission yield covariances, but simply best estimates and uncertainties. This situation is not unique as all libraries are facing this deficiency, firstly due to the lack of a defined format. An alternative approach is to provide a set of random fission yields, themselves reflecting covariance information. In this work, these random files are obtained combining the information from the JEFF library (fission yields and uncertainties) and the theoretical knowledge from the GEF code. Examples of this method are presented for the main actinides together with their impacts on simple burn-up and decay heat calculations.

show abstract

A Bayesian Monte Carlo method for fission yield covariance information

Cited by 29 publications

References 29 publications

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Correlationν̅_p − σ − χin the fast neutron range via integral information

Fission yield covariances for JEFF: A Bayesian Monte Carlo method

Contact Info

Product

Resources

About

A Bayesian Monte Carlo method for fission yield covariance information

Cited by 29 publications

References 29 publications

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Correlationν̅p − σ − χin the fast neutron range via integral information

Fission yield covariances for JEFF: A Bayesian Monte Carlo method

Contact Info

Product

Resources

About

Correlationν̅_p − σ − χin the fast neutron range via integral information