A New Nodal SN Transport Method for Three-Dimensional Hexagonal Geometry.

• IKEDA Hideaki

  Department of Nuclear Engineering, Faculty of Engineering, Osaka University Toden Software, Inc.

• TAKEDA Toshikazu

  Department of Nuclear Engineering, Faculty of Engineering, Osaka University

抄録

A new nodal SN transport method has been developed so as to perform accurate transport calculations in three-dimensional (3-D) hexagonal geometry. In the present method the neutron angular distributions of intra-node fluxes and transverse-leakage are represented using the S_N quadrature set, and the spatial distribution of neutron source is approximated by a quadratic polynomial expansion. Additionally, the authors have applied the nodal-equivalent finite difference algorithm to 3-D hexagonal geometry in order to establish a stable and efficient iterative scheme, <BR>The present method has been applied to a fast reactor benchmark problem. The results of the present method agree well with those of a Monte Carlo method, the difference in k_eff being less than 0.05%Δk. This shows high accuracy of the present method.

収録刊行物

• Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌）

  Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌） 31 (6), 497-509, 1994

  一般社団法人 日本原子力学会

キーワード

• transport calculations
• accuracy
• errors
• nodal SN method
• analytic intra-node flux distribution
• discontinuity
• transverse-leakage
• nodal-equivalent finite difference algorithm
• stabilization
• iterative convergence
• three-dimensional hexagonal geometry
• fast reactors
• keg
• flux
• neutron sources
• spatial distribution

詳細情報

• CRID: 1390001204095294592
• NII論文ID: 130000825634
• DOI: 10.3327/jnst.31.497
• COI: 1:CAS:528:DyaK2cXkvFeqtLw%3D
• ISSN: 18811248
• ISSN: 00223131
• 本文言語コード: en
• データソース種別:
  • JaLC
  • Crossref
  • CiNii Articles
• 抄録ライセンスフラグ: 使用不可