An Improvement of the Transverse Leakage Treatment for the Nodal SN Transport Calculation Method in Hexagonal-Z Geometry.
-
- SUGINO Kazuteru
- Department of Nuclear Engineering, Graduate School of Engineering, Osaka University
-
- TAKEDA Toshikazu
- Department of Nuclear Engineering, Graduate School of Engineering, Osaka University
書誌事項
- タイトル別名
-
- Improvement of the Transverse Leakage T
この論文をさがす
説明
To overcome the divergent behavior of the NSHEX code, a nodal SN code for hexagonal geometry, for some transport calculations, an improvement has been made in the calculation of the axial leakage. The axial leakage, previously calculated by using the quadratic transverse leakage approximation (QLA), is calculated by a new method of analytically treating the spatial distribution within a node, based on the axial homogeneity of the ordinary core. The verification tests were performed for the KNK-II model geometry of the NEACRP 3-D Neutron Transport Benchmarks and the large assembly-size KNK-II model. It is found that keff values obtained by introducing the new method agree with the reference Monte Carlo calculation results within 0.1% Δk/k for the KNK-II model, although the QLA method did not converge for two cases. Furthemore the new method succeeded in calculations for the large assembly-size model, in which the QLA method failed for all cases. Thus the new method has been found accurate and convergence achieved for the cases in which the QLA method failed.
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) 33 (8), 620-627, 1996
一般社団法人 日本原子力学会
- Tweet
キーワード
詳細情報 詳細情報について
-
- CRID
- 1390001204093736192
-
- NII論文ID
- 10002075234
-
- NII書誌ID
- AA00703720
-
- COI
- 1:CAS:528:DyaK28XmtVGmtLo%3D
-
- ISSN
- 18811248
- 00223131
-
- NDL書誌ID
- 4060415
-
- 本文言語コード
- en
-
- データソース種別
-
- JaLC
- NDL
- Crossref
- CiNii Articles
-
- 抄録ライセンスフラグ
- 使用不可