Feasibility study of decay heat uncertainty reduction using nuclear data adjustment method with experimental data

Kawamoto, Yosuke; Chiba, Go

doi:10.1080/00223131.2016.1238785

Cited by 9 publications

(6 citation statements)

References 14 publications

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“…It is a demonstration that the uncertainty study on SNF can be realized on a rather large scale, taking into account the specific irradiation and cooling details of each single assembly. Obviously additional work can be done based on the proposed method for a dedicated reactor, specific nuclear data libraries (especially for fission yields), possible data assimilation as presented in reference [32] to reduce calculate uncertainties, and also the application of the present methodology to burnup credit for SNF repository. One can also notice that these results are depending on the selection of covariance information.…”

Section: Future Studiesmentioning

confidence: 99%

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Rochman

Vasiliev

Dokhane

et al. 2018

EPJ Nuclear Sci. Technol.

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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.

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Section: Future Studiesmentioning

confidence: 99%

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Rochman

Vasiliev

Dokhane

et al. 2018

EPJ Nuclear Sci. Technol.

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“…The characteristics are the following (Fig. 7): Concerning EFBs, the experimental validation could be extended as well to give elements for short cooling times with the following experiments: -235 U th : LOTT experimental values (1973) [43] for cooling times between 17 s and more than 100 days and NGUYEN values (1997) [44] The experimental validation based on EFBs will have to be added to the experimental data assimilation process that only relies on MERCI-1 and CLAB assimilation for the moment; the objective will be to assimilate all this data at the same time, as recommended by [48] (for which only EFB data assimilation is performed), to obtain a final uncertainty capable of covering the largest DARWIN2.3 application domain, much more extensive than the current one covered by the experimental validation.…”

Section: Perspectives For the Determination Of An Enhanced Extended Umentioning

confidence: 99%

How to obtain an enhanced extended uncertainty associated with decay heat calculations of industrial PWRs using the DARWIN2.3 package

Huyghe

Vallet

Lecarpentier³

et al. 2019

EPJ Nuclear Sci. Technol.

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Decay heat is a crucial issue for in-core safety after reactor shutdown and the back-end cycle. An accurate computation of its value has been carried out at the CEA within the framework of the DARWIN2.3 package. The DARWIN2.3 package benefits from a Verification, Validation and Uncertainty Quantification (VVUQ) process. The VVUQ ensures that the parameters of interest computed with the DARWIN2.3 package have been validated over measurements and that biases and uncertainties have been quantified for a particular domain. For the parameter "decay heat", there are few integral experiments available to ensure the experimental validation over the whole range of parameters needed to cover the French reactor infrastructure (fissile content, burnup, fuel, cooling time). The experimental validation currently covers PWR UOX fuels for cooling times only between 45 minutes and 42 days, and between 13 and 23 years. Therefore, the uncertainty quantification step is of paramount importance in order to increase the reliability and accuracy of decay heat calculations. This paper focuses on the strategy that could be used to resolve this issue with the complement and the exploitation of the DARWIN2.3 experimental validation.

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“…This can be easily and efficiently carried out with the well-established generalized perturbation theory (GPT) for time-dependent problems (Lewins, 1960;Gandini, 1975). Since application of GPT to decay heat and delayed neutron activities calculations has been described in our previous papers in detail Kawamoto, 2016), it is omitted here.…”

Section: Sensitivity Calculations With Respect To Nuclear Datamentioning

confidence: 99%

“…Our research groups have worked on the uncertainty quantification of decay heat and delayed neutron yields independently so far Kawamoto, 2016). Since these two physical quantities are dependent on the same kind of the nuclear data as described above, consistent treatment is considered useful.…”

Section: Introductionmentioning

confidence: 99%

Consistent adjustment of radioactive decay and fission yields data with measurement data of decay heat andβ-delayed neutron activities

Chiba

2017

Annals of Nuclear Energy

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Decay heat and delayed neutron yields, which are important physical quantities in the field of the nuclear engineering, are dependent on common nuclear data such as radioactive decay data and fission yields data of fission product nuclides. In the present study, correlations between uncertainties of these two quantities are investigated. Nuclear data relevant to uranium-235 and plutonium-239 fissions with thermal neutron are adjusted consistently with a procedure based on Bayes' theorem using the measurement data of decay heat and delayed neutron activities. Numerical results suggest that the correlation between decay heat and delayed neutron activities uncertainties is not significant, and that independent treatments of decay heat or delayed neutron activities are possible. The effect of the consistent treatment of decay heat and delayed neutron activities is, however, observed in the adjustment results in some nuclear data such as uranium-235 thermal fission yields of yttrium-100m and zirconium-100.

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Feasibility study of decay heat uncertainty reduction using nuclear data adjustment method with experimental data

Cited by 9 publications

References 14 publications

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data

How to obtain an enhanced extended uncertainty associated with decay heat calculations of industrial PWRs using the DARWIN2.3 package

Consistent adjustment of radioactive decay and fission yields data with measurement data of decay heat andβ-delayed neutron activities

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