Analysis of ENRESA BWR samples: nuclide inventory and decay heat

Rochman, D.; Vasiliev, A.; Ferroukhi, H.; Muñoz, Ana; Antolin, Miriam Vazquez; Torres, Marta Berrios; Sanchez, Carlos Casado; Simeonov, Teodosi; Shama, Ahmed

doi:10.1051/epjn/2022007

Cited by 3 publications

(4 citation statements)

References 18 publications

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“…Regarding nuclear data, significant differences were found based on different libraries, mainly due to differences in uncertainties for the 134 Cs fission yield (a maximum decay heat uncertainty of 5-6% was found close to 2 years of cooling time with the ENDF/B-VIII.0 and JENDL-4.0 libraries). -For the ENRESA BWR samples [33], similar conclusions as for the PWR samples were found, with additionally a strong contribution from the void coefficient. One of these samples was also modelled with different assumptions (related to the interpretation of the description of the sample irradiation), leading to changes as high as 12% for the decay heat.…”

Section: Decay Heat Uncertaintysupporting

confidence: 74%

“…For the PIE samples, identical cases were selected by different institutes, such as the BWR ENRESA samples, SF95-5 from the Takahama-3 PWR reactor or the I2680 (A1-B23) sample from the BWR Gudremmingen reactor. In addition to these explicit choices by the EURAD partners, a number of external institutes also provided additional results, such as for the GU3 and ENRESA samples [23,33]. As mentioned, in the case of the ARI-ANE GU3 sample, the current activity from the OECD WPNCS Subgroup 10 will bring additional calculation cases for this sample, based on different irradiation history assumptions [34].…”

Section: Analysis Methodsmentioning

confidence: 99%

“…-The SCALE/Polaris code from the SCALE Code System, version 6.2.4, was used for modelling the nuclide inventiry of the BWR samples (details can be found in Ref. [33]). A two-dimensional single assembly was modelled with the exact irradiation history including the downtimes between cycles.…”

Section: Codes and Librariesmentioning

confidence: 99%

“…Apart from this high value, the impact of the void coefficient for the ENRESA study leads to an uncertainty of almost 6% for the 235 U concentration. Such value might be on the conservative side, as the considered variation of the void coefficient was large [33]. Another important factors are the sample enrichment (in the case of UO 2 samples), as well as the moderator temperature (both leading to 2-3%).…”

Section: Umentioning

confidence: 99%

See 3 more Smart Citations

On the estimation of nuclide inventory and decay heat: a review from the EURAD European project

Rochman

Dagan²,

Fiorito

et al. 2023

EPJ Nuclear Sci. Technol.

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In this work, a study dedicated to the characterization of the neutronics aspect of the Spent Nuclear Fuel (SNF), as part of the European project EURAD (Work Package 8), is presented. Both measured nuclide concentrations from Post Irradiation Examination samples and decay heat from calorimetric measurements are compared to simulations performed by different partners of the project. Based on these detailed studies and data from the published literature, recommendations are proposed with respect to best practices for SNF modelling, as well as biases and uncertainties for a number of important nuclides and the SNF decay heat for a cooling period from 1 to 1000 years. Finally, specific needs are presented for the improvement of current code prediction capabilities.

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Section: Decay Heat Uncertaintysupporting

confidence: 74%

Section: Analysis Methodsmentioning

confidence: 99%

Section: Codes and Librariesmentioning

confidence: 99%

Section: Umentioning

confidence: 99%

See 2 more Smart Citations

On the estimation of nuclide inventory and decay heat: a review from the EURAD European project

Rochman

Dagan²,

Fiorito

et al. 2023

EPJ Nuclear Sci. Technol.

Self Cite

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Improved Analysis of the Short-Term Station Blackout Accidents of the Peach Bottom Unit-2 Reactor with ASTEC Including Radiological Impact and Statistical Analysis with JRODOS

Murat,

Sanchez-Espinoza,

Gabrielli

et al. 2024

Nuclear Engineering and Design

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An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS

Rochman,

Algora,

Àlvarez-Velarde

et al. 2024

EPJ Nuclear Sci. Technol.

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This paper summarized the efforts performed to understand decay heat estimation from existing spent nuclear fuel (SNF), under the auspices of the Working Party on Nuclear Criticality Safety (WPNCS) of the OECD Nuclear Energy Agency. Needs for precise estimations are related to safety, cost, and optimization of SNF handling, storage, and repository. The physical origins of decay heat (a more correct denomination would be decay power) are then introduced, to identify its main contributors (fission products and actinides) and time-dependent evolution. Due to limited absolute prediction capabilities, experimental information is crucial; measurement facilities and methods are then presented, highlighting both their relevance and our need for maintaining the unique current full-scale facility and developing new ones. The third part of this report is dedicated to the computational aspect of the decay heat estimation: calculation methods, codes, and validation. Different approaches and implementations currently exist for these three aspects, directly impacting our capabilities to predict decay heat and to inform decision-makers. Finally, recommendations from the expert community are proposed, potentially guiding future experimental and computational developments. One of the most important outcomes of this work is the consensus among participants on the need to reduce biases and uncertainties for the estimated SNF decay heat. If it is agreed that uncertainties (being one standard deviation) are on average small (less than a few percent), they still substantially impact various applications when one needs to consider up to three standard deviations, thus covering more than 95% of cases. The second main finding is the need of new decay heat measurements and validation for cases corresponding to more modern fuel characteristics: higher initial enrichment, higher average burnup, as well as shorter and longer cooling time. Similar needs exist for fuel types without public experimental data, such as MOX, VVER, or CANDU fuels. A third outcome is related to SNF assemblies for which no direct validation can be performed, representing the vast majority of cases (due to the large number of SNF assemblies currently stored, or too short or too long cooling periods of interest). A few solutions are possible, depending on the application. For the final repository, systematic measurements of quantities related to decay heat can be performed, such as neutron or gamma emission. This would provide indications of the SNF decay heat at the time of encapsulation. For other applications (short- or long-term cooling), the community would benefit from applying consistent and accepted recommendations on calculation methods, for both decay heat and uncertainties. This would improve the understanding of the results and make comparisons easier.

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Analysis of ENRESA BWR samples: nuclide inventory and decay heat

Cited by 3 publications

References 18 publications

On the estimation of nuclide inventory and decay heat: a review from the EURAD European project

On the estimation of nuclide inventory and decay heat: a review from the EURAD European project

Improved Analysis of the Short-Term Station Blackout Accidents of the Peach Bottom Unit-2 Reactor with ASTEC Including Radiological Impact and Statistical Analysis with JRODOS

An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS

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