On the diffusion coefficient calculation in two-step light water reactor core analysis

Choi, Sooyoung; Smith, Kord; Kim, Hanjoo; Tak, Taewoo; Lee, Deokjung

doi:10.1080/00223131.2017.1299648

Cited by 24 publications

(9 citation statements)

References 10 publications

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“…The data preparation process for the fuel elements is historically based on the exact transport simulation of the fuel assembly with reflective boundary conditions [1]. The main complication of this approach is fact that the fuel assemblies are not in the infinite medium environment during the 3D calculation.…”

Section: Data Preparation Process and Reflector Calculationmentioning

confidence: 99%

“…The research reactors and NPPs are almost always operated in the critical state, but during the data preparation process, the infinite medium of the the fuel assemblies can be sub-critical or super-critical in case of their enrichment and geometry. Some solution of these issues can be found in the B1 approximation, described bellow or in the article [1]. The comparison of B1, P1 and CASMO methods can be found in the paper [1].…”

Section: Data Preparation Process and Reflector Calculationmentioning

confidence: 99%

“…Some solution of these issues can be found in the B1 approximation, described bellow or in the article [1]. The comparison of B1, P1 and CASMO methods can be found in the paper [1].…”

Section: Data Preparation Process and Reflector Calculationmentioning

confidence: 99%

See 2 more Smart Citations

Methods of Xs Data Preparation for Geometry With Fuel Dummy

Suk

2020

APP

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3D deterministic core calculation represents important category of the nuclear fuel cycle and safe Nuclear Power Plant operation. The appropriate solution was not published yet. Data preparation process for non-fuel elements of the core represents the challenge for scientists. This report briefly introduce the problem of the data preparation process and gives the information about new input format for macrocode PARCS (PMAXS). The best homogenization process approach is to prepare data in infinite lattice cell for fuel assemblies, which are placed next to the another fuel assembly. Data for fuel assembly located next to the non-fuel region are better with preparation in the real geometry with the real boundary conditions. Results of the neutron spectra study show that the PMAXS file format is well prepared for the 2 group calculation, but it is not well prepared for the multigroup calculations, however the XSEC file format still gave reasonable results.

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Section: Data Preparation Process and Reflector Calculationmentioning

confidence: 99%

Section: Data Preparation Process and Reflector Calculationmentioning

confidence: 99%

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Methods of Xs Data Preparation for Geometry With Fuel Dummy

Suk

2020

APP

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“…Three-step method firstly adopts detailed numerical analysis on fuel cell or lattice scale, the regional homogenization is carried out subsequently and the last step is the diffusion or transport calculation for the whole core. By contrast, pin-by-pin method has two steps (Choi et al, 2017), namely assembly transport calculation and a reactor core calculation. However, three-step method and pin-by-pin method both consider the fuel cell or assembly as a unity, so nuclide reaction inside the fuel area cannot be taken into consideration in detail.…”

Section: Introductionmentioning

confidence: 99%

Analysis of Categorical Subgroup Method for Resonance Self-Shielding Treatment

Zhang

et al. 2019

Front. Energy Res.

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To meet the requirements of one step lattice calculation on resonance effect, a self-developed design and construction of a resonance treatment code are composed based on subgroup method and HELIOS-1.11 library. Subgroup fixed source equations are solved by method of characteristics to get subgroup fluxes, which are subsequently used to deduce effective resonance cross sections combined with subgroup weights and subgroup levels. Bondarenko method is employed to handle resonance interference effect and a resonance category scheme and resonance geometry simplification method are introduced to improve efficiency. Benchmarks of single pin cells and assemblies of light water reactor are adopted for numerical validation and the calculating results indicate that this method can treat resonance effect both precisely and effectively.

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“…While rapidly progressing in the MC methods, deterministic approaches are still useful for design studies for new concepts in advanced reactors from the viewpoint of an equilibrium between calculation precision and computational cost. Following outstanding developments were done: in Ref [12], the GENESIS code was developed implementing the Legendre polynomial expansion of angular flux method; Ref [13] assessed consistent and rigorous precision of various methods for calculating the diffusion coefficients in a two-step reactor core analysis of light water reactors. New resonance self-shielding methods were proposed to treat for radially and azimuthally dependence in general multi-region geometry [14] and for the random medium of the high-temperature reactor lattice cells [15].…”

mentioning

confidence: 99%

Recent activities in the field of reactor physics

Fukushima

Tojo²

2019

Journal of Nuclear Science and Technology

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Reactor Physics that treat the essentials of how fission nuclear reactors work fundamentally has played important roles in safe operations and design studies of various types of nuclear reactors. From the latest activities in the field of reactor physics, this report summarizes some outstanding researches and developments published in scientific journals, including the Journal of Nuclear Science and Technology and others.

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On the diffusion coefficient calculation in two-step light water reactor core analysis

Cited by 24 publications

References 10 publications

Methods of Xs Data Preparation for Geometry With Fuel Dummy

Methods of Xs Data Preparation for Geometry With Fuel Dummy

Analysis of Categorical Subgroup Method for Resonance Self-Shielding Treatment

Recent activities in the field of reactor physics

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