Date:

2025-04-30

Title of Paper:

SCWR subchannel code ATHAS development and CANDU-SCWR analysis

Journal:

Nuclear Engineering and Design

Summary:

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.

Co-author:

Jianqiang Shan, Bo Zhang, Changying Li, Laurence K.H. Leung

Volume:

239 (2009)

Page Number:

1979–1987

Translation or Not:

No

Date of Publication:

2009-08-04