发布时间：2025-04-30

论文名称：SCWR subchannel code ATHAS development and CANDU-SCWR analysis

发表刊物：Nuclear Engineering and Design

摘要：A subchannel code (ATHAS) is developed for preliminary analyses of flow and enthalpy distributions and
cladding temperatures at supercritical water conditions. The code is applicable for transient and steady
state calculations. A number of heat-transfer correlations, frictional resistance correlations, and mixing
models have been implemented into the code as options for sensitivity analyses. In addition, a 3D heat
conduction model has been introduced to establish the cladding temperature. The results show that (1)
a CANFLEX [Inch,W.W.T., Thompson, P.D., Suk, H.C., 2000. Introduction of the new fuel bundle CANFLEX
into an existing CANDU reactor. In: Proceedings of the 12th Pacific Basin Nuclear Conference, October
29–November 2, Seoul, Korea.] bundle is appropriate for use in the CANDU supercritical water-cooled
reactor (SCWR) based on heat transfer analysis, (2) the selection of heat transfer, friction, and mixing
correlations has a significant impact on the prediction of the maximum cladding-surface temperature,
and (3) the inclusion of the 3D heat conduction in the calculation has provided a more realistic prediction
of the maximum cladding-surface temperature than assuming a uniform cladding temperature due to
the heterogeneous characteristic of rods.

合写作者：Jianqiang Shan, Bo Zhang, Changying Li, Laurence K.H. Leung

卷号：239 (2009)

页面范围：1979–1987

是否译文：否

发表时间：2009-08-04