본문 바로가기
KERD
논문KCI 등재

Treatment of non-resonant spatial self-shielding effect of double heterogeneous region

0

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

A new approximation method was proposed for treating the non-resonant spatial self-shielding effects of double heterogeneous region such as the double heterogeneous effect of VHTR fuel compact in the thermal energy range and that of BP compact with BISO. The method was developed based on the effective homogenization method and a spherical unit cell model with explicit coated layers and a matrix layer. The self-shielding factor was derived from the relation between the collision probabilities for a double heterogeneous compact and the effective cross section for the homogenized compact. First, the collision probabilities and transmission probabilities for all layers of the spherical model were calculated using conventional collision probability solver. Then, the effective cross section for the homogenized sphere cell representing the homogenized compact was obtained from the transmission probability calculated using the probability density function of a chord length. The verification calculations revealed that the proposed method can predict the self-shielding factor with a maximum error of 2.3% and the double heterogeneous effect with a maximum error of 200 pcm in the typical VHTR problems with various packing fractions and BP compact sizes.

Abstract

A new approximation method was proposed for treating the non-resonant spatial self-shielding effects of double heterogeneous region such as the double heterogeneous effect of VHTR fuel compact in the thermal energy range and that of BP compact with BISO. The method was developed based on the effective homogenization method and a spherical unit cell model with explicit coated layers and a matrix layer. The self-shielding factor was derived from the relation between the collision probabilities for a double heterogeneous compact and the effective cross section for the homogenized compact. First, the collision probabilities and transmission probabilities for all layers of the spherical model were calculated using conventional collision probability solver. Then, the effective cross section for the homogenized sphere cell representing the homogenized compact was obtained from the transmission probability calculated using the probability density function of a chord length. The verification calculations revealed that the proposed method can predict the self-shielding factor with a maximum error of 2.3% and the double heterogeneous effect with a maximum error of 200 pcm in the typical VHTR problems with various packing fractions and BP compact sizes.

참고문헌 (15)

  1. 조진영, "Improvement and Verification of the DeCART code for HTGR Core Physics Analysis", Nuclear Engineering and Technology, 51(1), pp.13~30 (2019), 한국원자력학회[DOI]
  2. R. Sanchez, "A statistical analysis of the double heterogeneity problem", Ann. Nucl. Energy, 18, pp.371~395 (1991)
  3. R. Sanchez, "Treatment of the Double Heterogeneity with the Method of Characteristics", Proc. PHYSOR 2002 (2002)
  4. S. Y. Choi, "Resonance treatment using pin-based pointwise energy slowing-down method", J. Comput. Phys, 330, pp.134~155 (2017)
  5. T. Y. Han, "Extension of pin-based point-wise energy slowing-down method for VHTR Fuel with double heterogeneity", Energies, 14, pp.2179~ (2021)
  6. V.M. Shmakov, "Effective Cross Sections for Calculations of Criticality of Dispersed Media", Proc. PHYSOR 2000 (2000)
  7. T. Yamamoto, "Extension of effective cross section calculation method for neutron transport calculations in particle-dispersed media", J. Nucl. Sci. Technol, 43, pp.77~87 (2006)
  8. D. She, "An equivalent homogenization method for treating the stochastic media", Nucl. Sci. Eng, 185, pp.351~360 (2017)
  9. M. L. Williams, "Resonance self-shielding methodologies in SCALE 6", Nucl. Technol, 174, pp.149~168 (2011)
  10. DRAGON theory manual, Part 1: collision probability calculations, "G. Marleau", Department de genie mecanique, Ecole Polytechnique de Montreal, ~, pp.Tech. Rep. IGE-236 Revision 1 (2001)
  11. K.M. Case, "Introduction to the theory of neutron diffusion", pp.21~ (1953)
  12. A. Gil, "Numerical Methods for Special Functions, Society for Industrial and Applied Mathematics" (2007), Society for Industrial and Applied Mathematics. SIAM
  13. Prismatic Coupled Neutronics, "Thermal Fluids Transient Benchmark of the MHTGR-350 MW Core Design: Benchmark Definition", J. Ortensi, 2013, NEA[DOI]
  14. 심형진, "MCCARD: MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS", Nuclear Engineering and Technology, 44(2), pp.161~176 (2012), 한국원자력학회
  15. Y. H. Kim, "Elimination of double-heterogeneity through a reactivity-equivalent physical transformation", Proc. GLOBAL (2005)

관련 논문AI추천

Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCXCao Liangzhi, He Qingming, Li Yunzhao, Qin Shuai, Wang Yongping, Wu Hongchun, Wu Yuxuan한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제9호Development of a general framework of resonance self-shielding treatment for broad-spectrum reactor lattice physics calculationCao Wei, Gilad Erez, Qin Shuai, Wu Shifu, Yu Jialei, Zhang Jinchao, Zhang Qian, Zhao Qiang, Zou Hang한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제10호Analyses of on-the-fly generation of spectral superhomogenization factors for multigroup whole core calculation employing pin-wise slowing-down solutions제승욱, 주한규한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제3호Cross section generation for a conceptual horizontal, compact high temperature gas reactorDownar Thomas, Jabaay Daniel, Kang Junsu, Kochunas Brendan, Seker Volkan, Ward Andrew한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제3호Geometrical shape and self-shielding effect of burnable poison particles on pin-in block type HTGR neutronic performanceSambuu Odmaa, Terbish Jamiyansuren한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제6호Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysisFeng Kuaiyuan, Gu Hanyang, Guo Hui, Song Qufei, Vidal Jean-François, Wu Yiwei한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제7호

이 간행물의 다른 논문 (39건)