Resonance Treatment Based on Ultra-fine-group Spectrum Calculation in the AEGIS Code

Sugimura, Naoki; Yamamoto, Akio

doi:10.3327/jnst.44.958

Cited by 8 publications

(6 citation statements)

References 4 publications

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“…A resulting spectrum is used as a weighting function for condensation to the target group structure. However, this approximation-free method is not practical at all, and thus many approximated ways have been proposed [10,11,[46][47][48], to which the EDC method belongs. Instead of solving the slowing down problem in an explicit heterogeneous lattice geometry using the DFEM-SN solver, the heterogeneous lattice geometry is decoupled to multiple 1D pin-cell problems that preserve the Dancoff factor calculated in the reference geometry using the DFEM-SN solver.…”

Section: Equivalent Dancoff Factor Cell (Edc) Methodsmentioning

confidence: 99%

Cross Section Generation Capability in Griffin

Park¹,

Lee²,

Jung³

et al. 2021

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Section: Equivalent Dancoff Factor Cell (Edc) Methodsmentioning

confidence: 99%

Cross Section Generation Capability in Griffin

Park¹,

Lee²,

Jung³

et al. 2021

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“…From the reproducibility of the SPH method, reaction rates at the mth burnup step obtained by the SPH method become equivalent to those obtained with a fine condition. Therefore, Equation (9), which describes the equivalence of reaction rates, is satisfied,…”

Section: Discretization Errors In the Sph Methodsmentioning

confidence: 99%

“…In this paper, a calculation scheme using the SPH method is considered as the first step of this study. The SPH method is a kind of equivalence methods, by which a reference result can be reproduced with a coarse calculation condition, and is used to improve calculation efficiency in the previous studies [8][9][10]. Although the SPH method is originally a technique for reducing spatial homogenization errors, the SPH method can be used also for reducing discretization errors due to coarse ray tracing condition as described above.…”

Section: Introductionmentioning

confidence: 99%

Reduction of MOC discretization errors through a minimization of source ratio variances

Tabuchi

Yamamoto

Endo

et al. 2016

Journal of Nuclear Science and Technology

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A new technique to reduce discretization errors for ray tracing in the method of characteristics (MOC) is proposed focusing on depletion calculations of single and multi-assembly geometries. In order to efficiently carry out depletion calculations, a calculation scheme using the superhomogenization (SPH) method can be used. However, the discretization errors are caused by changes of neutron sources and total cross sections according to a depletion. This fact means that improvement of accuracy cannot be expected by the calculation scheme with the SPH method when changes of the above parameters are significant. In order to mitigate this problem, a new approach is developed. In the new approach, the discretization errors are reduced by minimizing a variance of a certain parameter which is composed of a ratio of neutron source to total cross section. The verification results suggest that accuracy is degraded by the SPH method as expected especially in a geometry where neutron sources and total cross sections are drastically changing through a depletion. On the other hand, the new approach gives more accurate results compared to the conventional MOC in all calculation cases. Consequently, improvement of calculation efficiency by the new approach is confirmed.

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“…It has been reported that a coarse-energy group calculation does not reproduce neutron multiplication factor of a reference fine-energy group calculation even if fine-group neutron flux obtained from the reference calculation is used as a weight function in cross section group collapsing (Sugimura and Yamamoto, 2007).…”

Section: Corrections For Current-weighted Total Cross Sectionmentioning

confidence: 99%

Advanced Bondarenko method for resonance self-shielding calculations in deterministic reactor physics code system CBZ

Chiba

Narabayashi

2016

Annals of Nuclear Energy

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The advanced Bondarenko method for resonance self-shielding calculations is devised and proposed. This method is based on three numerical methods; the Bell factor optimization for accurate fuel escape probability representation, extension of resonance interference factors and correction factors for current-weighted total cross sections. A 107-group library for light water reactor applications based on the advanced Bondarenko method is generated for a reactor physics code system CBZ. Performance of the CBZ code with this 107-group library is examined against a suit of light water reactor cell problems. The infinite neutron multiplication factors calculated with CBZ agree with reference continuous-energy Monte Carlo solutions within 0.15%∆k/kk ′ differences, and no significant biases on fuel compositions and geometrical specifications are observed. Energy-averaged cross sections are also examined. Numerical tests reveal that significant accuracy improvements in resonance self-shielding calculations are realized by adopting the advanced Bondarenko method without any significant increase of computational burden.

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Resonance Treatment Based on Ultra-fine-group Spectrum Calculation in the AEGIS Code

Cited by 8 publications

References 4 publications

Cross Section Generation Capability in Griffin

Cross Section Generation Capability in Griffin

Reduction of MOC discretization errors through a minimization of source ratio variances

Advanced Bondarenko method for resonance self-shielding calculations in deterministic reactor physics code system CBZ

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