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

Yamamoto, Toru; Ando, Yasumasa; Sakai, Tomohiro; Sakurada, Koichi; Umano, Takuya

doi:10.3327/jnst.46.599

Cited by 5 publications

(4 citation statements)

References 12 publications

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“…In order to extend database for the above validation study (ii), the Japan Nuclear Energy Safety Organization (JNES) has implemented a core physics experimental program FUBILA [2][3][4][5][6][7][8][9][10][11][12]. 1 It aimed at obtaining the core physics characteristics of full MOX BWR cores, which consisted of high Pu-content BWR MOX assemblies for achieving high burnup of fuel.…”

Section: Introductionmentioning

confidence: 99%

“…Part of the program was the measurements of various types of reactivity effects, which were performed using a neutron source multiplication method in sub-critical experimental cores. Yamamoto et al [11] have reported the experimental method and results, and the neutronics analysis results. The other part of the experiments was conducted at the critical state of the experimental cores, where critical masses, core fission rate distributions and other core characteristics were obtained.…”

Section: Introductionmentioning

confidence: 99%

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Neutronics analysis of full MOX BWR core simulation experiments – FUBILA: Part 2

Yamamoto

Sakai

Ando

et al. 2012

Journal of Nuclear Science and Technology

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A part of the experimental program FUBILA was dedicated to the study of core physics characteristics of full MOX BWR cores by testing five experimental cores: a core inserted with a B 4 C control blade, a core loaded with UO 2 fuel rods, the core loaded with Gd 2 O 3 -UO 2 fuel rods, a core loaded with 10 6 10 MOX assemblies and a core loaded with time-elapsed MOX fuel. The present article describes analysis results of the experimental data with deterministic analysis codes and a continuous energy Monte Carlo code coupled with major nuclear data libraries. The calculated critical k eff' s with the Monte Carlo calculations range from 0.999 to 1.007. Those of the transport calculations with sixteen energy groups are close to those of the Monte Carlo calculations while those of diffusion calculations with the same sixteen energy groups are systematically smaller by 70.3 to 70.5% Dk than those of the Monte Carlo calculations. The RMSs of differences between the calculated and measured core radial fission rates are 2 to 3%, 1 to 2%, and 1 to 2% for the diffusion, transport and Monte Carlo calculations, respectively. For the analysis of the Gd 2 O 3 -UO 2 fuel rod loaded core, the C/Es of the radial fission rates were improved by adopting a detailed lattice calculation model and a newly measured thermal and resonance cross-sections of Gadolinium.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Neutronics analysis of full MOX BWR core simulation experiments – FUBILA: Part 2

Yamamoto

Sakai

Ando

et al. 2012

Journal of Nuclear Science and Technology

Self Cite

View full text Add to dashboard Cite

show abstract

“…A complete analysis of these experiments can be found in Ref. 9), where MSM factors have been calculated in order to compensate for the spatial and energy perturbations in the detector due to the spectrum hardening.…”

Section: C/e On Reactivity Worthmentioning

confidence: 99%

“…The reactivity worth of increasing void fractions, from 0 to 70%, has been measured by the subcritical method 8,9) in the REF core. The void fraction is simulated as explained in Sec.…”

Section: C/e On Reactivity Worthmentioning

confidence: 99%