Spent fuel characterization analysis using various nuclear data libraries

Čalič, Dušan; Kromar, Marjan

doi:10.1016/j.net.2022.04.009

Cited by 6 publications

(4 citation statements)

References 14 publications

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“…The results showed that the fission products contribute to the decay heat power mainly in the short storage period (<50 years). As highlighted in [4], the accuracy of the results obtained from analytical and numerical calculations depends on the degree of the accuracy of available data and on the use of appropriate cross-section libraries [5][6][7]. At present, most of the calculations of spent fuel characteristics after in-service operation are performed by means of validated numerical codes such as ORIGEN (Oak Ridge Isotope Generation, developed at ORNL, Oak Ridge, TN, USA) or KORIGEN (FZK, Hannover, Germany).…”

Section: Storage Strategiesmentioning

confidence: 99%

“…At present, most of the calculations of spent fuel characteristics after in-service operation are performed by means of validated numerical codes such as ORIGEN (Oak Ridge Isotope Generation, developed at ORNL, Oak Ridge, TN, USA) or KORIGEN (FZK, Hannover, Germany). However, the behaviour out-ofreactor, at interim storage or final disposal, requires a detailed isotopic characterisation and radioactivity evaluation [6][7][8].…”

Section: Storage Strategiesmentioning

confidence: 99%

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Assessment of Spent Nuclear Fuel in Ukrainian Storage System: Inventory and Performance

Dolin,

Lo Frano,

Cancemi

2024

Energies

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It is of meaningful importance to evaluate the performance of all the nuclear facilities, and particularly those part of such buildings where spent nuclear fuel (SNF) is stored to assess what kinds of consequences are anomalous/abnormal or to determine what types of accident events may occur. In this preliminary study, the strategies adopted for the management of SNF, and the risk related to them are discussed. The aim of this study is to evaluate the total radioactivity inventory characterising Ukrainian nuclear facilities, including storage facilities. The dataset used to calculate the total activity associated with nuclear fuel is provided and discussed. For the evaluation, it is considered that a SNF pool in VVER-1000 is designed to store 687 fuel assemblies, and 670 are in VVER-440. When it is half full, which is the case for 15 Ukrainian units, it will store about 2200 tU containing up to 1·1019 Bq of 137Cs, 7·1018 Bq of 90Sr, and 1·1019 Bq of TUE. This study focuses particularly on the total activity of the SNF stored at the Zaporozhye plant, the biggest nuclear plant in Europe, and the risk posed by the potential loss that cooling the plant could incur because of pond water level variation. The results of the analysis of the Zaporozhye NPP behaviour suggest that the water flow rate which keeps the SNF pool temperature constant is about 200,000 m3·day−1. Therefore, the water level in the pond should not be lower than 1.5–2 m; otherwise, the plant will need an additional source of water of more than 200,000 m3 per day to guarantee safe storage of SNF.

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Section: Storage Strategiesmentioning

confidence: 99%

Section: Storage Strategiesmentioning

confidence: 99%

Assessment of Spent Nuclear Fuel in Ukrainian Storage System: Inventory and Performance

Dolin,

Lo Frano,

Cancemi

2024

Energies

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“…-17 PIE samples were used to calculate nuclide compositions, uncertainties, and biases, for 4 ARIANE samples (GU1, GU3, BM1, BM3), 8 ENRESA samples (not available in SFCOMPO), the U1 PROTEUS sample (also not available in SFCOMPO), 2 Takahama samples (SF95-4 and SF95-5), and 2 Gundremmingen samples (B23-A1-I2680 and C5-B23-K2680), with the addition of 2 computational cases (S1.PWR and krsko.PWR [14,15]), -271 calorimetric measurements from CLAB (labelled herein as CLAB-2006), GE-Morris, HEDL facilities and the "SKB-Vattenfall" blind test were analyzed for the assembly average decay heat [16][17][18][19], and the decay heat from the 17 (not measured) PIE samples. Detailed studies were independently published for a number of cases, see references [20][21][22][23][24][25][26][27][28][29][30][31][32]50]; summaries are presented in Tables 1 and 2.…”

Section: Studied Casesmentioning

confidence: 99%

“…-In references [14,26], the case of a PWR UO 2 assembly is considered, with 4.95% enrichment and a burnup value of 60 MWd/kg. Changes in simulation codes indicate a maximum effect on the assembly decay heat of 4%.…”

Section: Decay Heat Uncertaintymentioning

confidence: 99%

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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Optimizing spent nuclear fuel cask loading for VVER-440 fuel

Lovecký,

Závorka

2024

Nuclear Engineering and Technology

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Spent fuel characterization analysis using various nuclear data libraries

Cited by 6 publications

References 14 publications

Assessment of Spent Nuclear Fuel in Ukrainian Storage System: Inventory and Performance

Assessment of Spent Nuclear Fuel in Ukrainian Storage System: Inventory and Performance

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

Optimizing spent nuclear fuel cask loading for VVER-440 fuel

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