Analysis of High Moderation Full MOX BWR Core Physics Experiments BASALA

Ishii, Kazuya; Ando, Yasumasa; Takada, Naoyuki; Kan, Taro; Sasagawa, Masaru; Kikuchi, T.; Yamamoto, Toru; Kanda, Ryoji; Umano, Takuya

doi:10.3327/taesj2002.4.45

Cited by 10 publications

(11 citation statements)

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“…It is observed for the mixing of boron in the moderator that differences in the C/Es are small among the calculation methods and the nuclear data libraries used, and the calculations generally overestimate the reactivity worth except for those of 978 ppm even though the measurement error and the error due to the uncertainty in the boron concentration are taken into account. A similar trend was also reported by Ishii et al 9) as part of the results of the MISTRAL and BASALA programs.…”

Section: Analysis Resultssupporting

confidence: 71%

“…As the above validation study (ii), core physics experimental data are available from MISTRAL [2][3][4][5][6] and BASALA [7][8][9] programs that have been implemented in the EOLE critical facility of the Cadarache Center of the Commission of Atomic Energy (CEA) in France. The experiments of these programs were dedicated to an advanced LWR MOX core concept that is characterized by high-moderation full-MOX LWR cores.…”

Section: Introductionmentioning

confidence: 99%

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Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR

Yamamoto

Ando

Sakai

et al. 2009

Journal of Nuclear Science and Technology

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A core physics experimental program FUBILA has been performed to study core physics characteristics of full-MOX BWR cores consisting of high Pu-enriched MOX assemblies for high burnups. The program includes the measurement of reactivity worth, which is essential in operating BWR cores. The reactivity worth is due to the reactivity caused by (1) changes in the in-channel void fraction of assemblies, (2) the insertion of a B 4 C control blade, (3) Gd 2 O 3 -UO 2 rods and UO 2 rods in assemblies, and (4) the mixing of boron in a moderator related to a stand-by liquid control system. The reactivity worth was measured by the modified neutron source multiplication method using the reactivity worth of a pilot rod as a reference worth. The measured reactivity worth was determined by processing count rates of neutron detectors taking into account the detector efficiency and effective neutron source intensity analyzed by three-dimensional transport calculations. Comparing the measured reactivity worth with the results obtained by deterministic calculation methods and a Monte Carlo calculation method, the accuracy of the calculations was evaluated. The calculated results generally well reproduce the measurements, except for the boron reactivity worth in the moderator, for which the calculations overestimate the reactivity worth.

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Section: Analysis Resultssupporting

confidence: 71%

Section: Introductionmentioning

confidence: 99%

Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR

Yamamoto

Ando

Sakai

et al. 2009

Journal of Nuclear Science and Technology

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“…In the analysis with the continuous energy Monte Carlo code MVP [14] and JENDL-3.2 carried out by NUPEC [12], the average of the critical keffective values was 1.0086. The results calculated using the direct response matrix method agreed very well with the results calculated using the continuous energy Monte Carlo code.…”

Section: Analysis Processmentioning

confidence: 99%

“…This article describes the analysis results of the MOX critical experiments BASALA [10][11][12] for further verification of the pin-by-pin core analysis method using the three-dimensional direct response matrix.…”

Section: Introductionmentioning

confidence: 99%

Analysis of the MOX critical experiments BASALA by pin-by-pin core analysis method using three-dimensional direct response matrix

Ishii

Mitsuyasu

Hino

et al. 2012

Journal of Nuclear Science and Technology

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An analysis of the MOX critical experiments BASALA was performed to verify the pin-by-pin core analysis method using a three-dimensional direct response matrix. The BASALA experiments simulate full MOX BWR cores, and they were carried out in the EOLE critical facility of the French Atomic Energy Commission (CEA) by the Nuclear Power Engineering Corporation (NUPEC) in collaboration with CEA. The BASALA experimental cores are very heterogeneous because their size is much smaller than that of commercial power plants. The main features of the pin-by-pin core analysis method using the three-dimensional direct response matrix are that the response matrix can reflect the intra-assembly heterogeneous effect, the diffusion approximation is not involved, and the fuel rod fission rate can be directly evaluated. The maximum difference of the critical k-effective values among all nine cores analyzed was about 0.4% Dk. The root mean square differences between the calculated and measured radial fuel rod fission rate distributions in the test assembly of all cores were within 1.8% and nearly comparable to measurement error. The calculated results of the reactivity worth agreed with the measured results within 9%. These good agreements mean that the pin-by-pin core analysis method using the three-dimensional direct response matrix accurately reflects the effects of the intra-and inter-assembly heterogeneities in heterogeneous systems like the BASALA experimental cores.

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“…Verification work for these parameters has commonly been using measured data of power distributions of zeropower core physics experiments with fresh mock-up fuel assemblies. [5][6][7] However, studies using data of irradiated fuel assemblies are sparse because such measurements usually have to be done in postirradiation facilities. Misu et al 8) reported experimental data of rod-by-rod distributions of 140 Ba representing fission rate distributions on irradiated BWR 9 Â 9-1 UO 2 and MOX assemblies using gamma scanning in the irradiated fuel storage pool of the Gundremmingen BWR.…”

Section: Introductionmentioning

confidence: 99%

Analysis of Rod-by-Rod FP Inventory Distributions in BWR 8×8 UO2 Assemblies Using Lattice Physics Method

Yamamoto

Yamamoto²

2008

J. Nucl. Sci. Technol.

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Fuel rod gamma-ray spectrometry was performed for one-, two-, three-, and five-cycle irradiated BWR 8 Â 8-4 fuel assembles, and relative rod-by-rod FP inventory distributions of 137 Cs, 134 Cs, 106 Ru, and 95 Zr were obtained for the upper and lower axial height nodes of the assemblies. The measured data was corrected for the difference in gamma-ray transmission between UO 2 and Gd 2 O 3 -UO 2 rods. These distributions were compared with those calculated using the collision probability method, Pij, of the SRAC code system with an infinite lattice model of the fuel assembly. The calculated results generally well reproduce the measured distributions, and the accuracy of the analysis method of the present study was evaluated to be 1 to 2% for the inventory distributions of 137 Cs, 2 to 3% for 134 Cs, 2 to 3% for 106 Ru, and 2 to 3% for 95 Zr, which represent the distributions of the burn-up, the thermal flux multiplied by the burn-up, the buildup of 239 Pu, and the fission rate at the end of the fuel discharge cycle, respectively. One of the notable results of the analysis of this study is that the FP inventories for the Gd 2 O 3 -UO 2 rods were underestimated in most cases.

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Analysis of High Moderation Full MOX BWR Core Physics Experiments BASALA

Cited by 10 publications

References 0 publications

Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR

Analysis of Reactivity Measurements in Core Physics Experiments on Full-MOX BWR

Analysis of the MOX critical experiments BASALA by pin-by-pin core analysis method using three-dimensional direct response matrix

Analysis of Rod-by-Rod FP Inventory Distributions in BWR 8×8 UO2 Assemblies Using Lattice Physics Method

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