Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors

Ushio, Tadashi; Takeda, Toshikazu; Mori, Masashi

doi:10.3327/jnst.40.464

Cited by 15 publications

(9 citation statements)

References 3 publications

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“…This type of the Pu content distribution is common in MOX fuel assembly design of PWR to mitigate pin power peaking at assembly peripheral region. Neutron transport calculations in fuel assemblies were carried out by the NELAT code, 3) which is based on the characteristics method. The NELAT code is mainly used for cell and assembly calculations of light water reactors and has some features for accurate calculations, i.e.…”

Section: Numerical Resultsmentioning

confidence: 99%

Approximate Treatment of Thermal Expansion Effect in Lattice Transport Calculations

Yamamoto

Kitamura

Yamane

2004

Journal of Nuclear Science and Technology

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In this paper, thermal expansion effect on neutronics characteristics is approximately taken into account by a correction on cross sections. Dimensions of reactor core components depend on their temperatures due to the thermal expansion phenomena. However, the variation of calculation geometry requires considerable computational load for trajectory based lattice transport calculations such as the characteristics method since ray tracing must be re-executed. Therefore, if a correction on cross sections can accurately capture the effect of geometrical variation due to the thermal expansion, computation time of a lattice transport calculation that treat temperature variation can be reduced. Three different corrections on cross sections were tested in PWR fuel assembly geometry using UO 2 and MOX fuels. It was found that the correction of cross sections that preserves neutron attenuation in a region almost reproduce the reference calculation that explicitly considers geometrical variation due to the thermal expansion. The result of this paper will be useful for lattice calculations in production analysis since material temperatures are frequently changed in such analysis to cover various reactor conditions.

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Section: Numerical Resultsmentioning

confidence: 99%

Approximate Treatment of Thermal Expansion Effect in Lattice Transport Calculations

Yamamoto

Kitamura

Yamane

2004

Journal of Nuclear Science and Technology

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“…• Anisotropic scattering cross sections up to the P3 component are stored for light nuclides (e.g., H, O), structural nuclides (e.g., Fe) and major heavy nuclides (e.g., U). This is because the impact of the anisotropic scattering could be significant for MOX fuels in which angular flux distributions show skewed shapes [5]. Furthermore, advanced fuel assemblies appearing in generation-IV reactors have strong heterogeneity; thus, they also require precise treatment of anisotropic scattering.…”

Section: Cross Section Librarymentioning

confidence: 99%

“…Furthermore, advanced fuel assemblies appearing in generation-IV reactors have strong heterogeneity; thus, they also require precise treatment of anisotropic scattering. The previous studies on anisotropic scattering suggest that treatment up to the P3 components has sufficient accuracy for highly heterogeneous fuels such as MOX [5].…”

Section: Cross Section Librarymentioning

confidence: 99%

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Aegis: An Advanced Lattice Physics Code for Light Water Reactor Analyses

Yamamoto¹,

Endo²,

Tabuchi³

et al. 2010

Nuclear Engineering and Technology

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“…intersects of regions, hence large discretization error would be observed in such situation. To avoid this problem, the macroband method [2] was developed and applied for MOC in the previous study [3]. In the * Corresponding author.…”

Section: Introductionmentioning

confidence: 99%

Preservation of transmission probabilities in the method of characteristics

Tabuchi

Yamamoto

Endo

et al. 2013

Journal of Nuclear Science and Technology

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An efficient calculation scheme for the method of characteristics, which allows coarser ray separation width, is newly proposed. Effective lengths of characteristics lines are evaluated from the viewpoint of preservation of transmission probability in the present method. The effective lengths to preserve transmission probabilities can be rigorously estimated through detailed numerical integrations. However, calculation and storage of all effective lengths is inefficient since the transmission probabilities depend on many parameters such as azimuthal angle, polar angle, position of characteristics line, and total cross section. To resolve this issue, in this paper, the analytical equations for the effective lengths are derived from an assumption that distribution function of actual characteristics lengths can be expressed by a linear function. The new approach introduced in this paper is named as transmission probability preservation through linear approximation (TPPL). Verification results indicate that accurate results can be obtained by the TPPL even if ray separation width becomes coarse.

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Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors

Cited by 15 publications

References 3 publications

Approximate Treatment of Thermal Expansion Effect in Lattice Transport Calculations

Approximate Treatment of Thermal Expansion Effect in Lattice Transport Calculations

Aegis: An Advanced Lattice Physics Code for Light Water Reactor Analyses

Preservation of transmission probabilities in the method of characteristics

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