Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems

Suyama, Kenya; Murazaki, Minoru; Ohkubo, Kiyoshi; Nakahara, Y.; Uchiyama, Gunzo

doi:10.1016/j.anucene.2011.01.025

Cited by 11 publications

(7 citation statements)

References 13 publications

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“…The result previously published by Suyama et al for the same benchmark specification but using different methodology based on the SWAT code, shows good agreement for 36 matches (65%) [2]. Hence, the results of MCB modeling in the more accurate way refl ect the physics of the 17G fuel assembly.…”

Section: Comparative Analysissupporting

confidence: 64%

“…The similar overestimation but in the range of 3-5% was presented by Suyama et al [2] which indicates to some inconsistencies in the benchmark specifi cation. The most probable reasons for the U-235 overestimation might be: -erroneous measurements of reference U-235 concentrations -the overestimation in U-235 concentrations was observed for MCB and SWAT modeling,…”

Section: U-235mentioning

confidence: 48%

“…This, in turn may result in the same burnup values for different number of fi ssions and following Brought to you by | MIT Libraries Authenticated Download Date | 5/11/18 11:56 AM inconsistencies in fi nal isotopic fuel composition. Therefore, the usage of aforementioned burnup defi nition is not recommended and the new FIMA 2) unit was introduced. The FIMA unit indicates the decrement of heavy metal during irradiation and is commonly used for normalization of the burnup calculations.…”

Section: Samplesmentioning

confidence: 99%

“…The knowledge about the fi nal actinide concentrations for the comparative analysis and associated improvement of the numerical tools is seldom desired and in consequence hardly available. The Ohi-2 irradiation experiment was chosen for the comparative analysis due to availability of the measured actinide concentrations and vast set of additional operational and design parameters [2].…”

mentioning

confidence: 99%

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Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR

Oettingen

Cetnar

2015

Nukleonika

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In the paper, we assess the accuracy of the Monte Carlo continuous energy burnup code (MCB) in predicting final concentrations of major actinides in the spent nuclear fuel from commercial PWR. The Ohi-2 PWR irradiation experiment was chosen for the numerical reconstruction due to the availability of the final concentrations for eleven major actinides including five uranium isotopes (U-232, U-234, U-235, U-236, U-238) and six plutonium isotopes (Pu-236, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242). The main results were presented as a calculated-to-experimental ratio (C/E) for measured and calculated final actinide concentrations. The good agreement in the range of ±5% was obtained for 78% C/E factors (43 out of 55). The MCB modeling shows significant improvement compared with the results of previous studies conducted on the Ohi-2 experiment, which proves the reliability and accuracy of the developed methodology.

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Section: Comparative Analysissupporting

confidence: 64%

Section: U-235mentioning

confidence: 48%

Section: Samplesmentioning

confidence: 99%

mentioning

confidence: 99%

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Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR

Oettingen

Cetnar

2015

Nukleonika

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“…The reference data applied in the analysis are mainly based on the two scientific publications: the paper of T. Adachi et al [1] and the paper of K. Suyama et al [2]. The papers include the comprehensive knowledge about performed post irradiation examination of the spent fuel samples, irradiation history and fuel assembly design.…”

Section: Introductionmentioning

confidence: 99%

Influence of FIMA burnup on actinides concentrations in PWR reactors

Oettingen

Skolik

2016

E3S Web Conf.

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Abstract. In the paper we present the study on the dependence of actinides concentrations in the spent nuclear fuel on FIMA burnup. The concentrations of uranium, plutonium, americium and curium isotopes obtained in numerical simulation are compared with the result of the post irradiation assay of two spent fuel samples. The samples were cut from the fuel rod irradiated during two reactor cycles in the Japanese Ohi-2 Pressurized Water Reactor. The performed comparative analysis assesses the reliability of the developed numerical set-up, especially in terms of the system normalization to the measured FIMA burnup. The numerical simulations were preformed using the burnup and radiation transport mode of the Monte Carlo Continuous Energy Burnup Code -MCB, developed at the

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The design and simulation of a new spent fuel pool passive cooling system

Zheng

Wang

et al. 2013

Annals of Nuclear Energy

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Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems

Cited by 11 publications

References 13 publications

Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR

Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR

Influence of FIMA burnup on actinides concentrations in PWR reactors

The design and simulation of a new spent fuel pool passive cooling system

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