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- Duerigen Susan
- Helmholtz-Zentrum Dresden-Rossendorf
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- Fridman Emil
- Helmholtz-Zentrum Dresden-Rossendorf
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- Kliem Soeren
- Helmholtz-Zentrum Dresden-Rossendorf
抄録
DYN3D is a 3D nodal diffusion code for steady-state and transient analyses of Light-Water Reactors (LWRs) with square and hexagonal fuel assembly geometries. Currently, several versions of the DYN3D code are available including a multi-group diffusion and a simplified P_3 (SP_3 ) neutron transport option. In this work, the multi-group SP_3 method based on trigonal-z geometry was developed. The method is applicable to the analysis of reactor cores with hexagonal fuel assemblies and allows flexible mesh refinement, which is of particular importance for VVER-type Pressurized Water Reactors (PWRs) as well as for innovative reactor concepts including block type High-Temperature Reactors (HTRs) and Sodium Fast Reactors (SFRs). In this paper, the theoretical background for the trigonal SP_3 methodology is outlined and the results of a preliminary verification analysis are presented by means of two VVER-440 single assembly test examples with different material compositions. The accordant cross sections and reference solutions were produced by the Monte Carlo code SERPENT. The DYN3D results are shown for 2 and 8 energy groups, respectively, and are in good agreement with the reference solutions. The deviation in the nodal power distribution is about 1%.
収録刊行物
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- Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
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Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2011.19 (0), _ICONE1944-_ICONE1944, 2011
一般社団法人 日本機械学会
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詳細情報 詳細情報について
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- CRID
- 1390001205881706880
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- NII論文ID
- 110009957130
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- ISSN
- 24242934
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可