Date:

2025-04-30

Title of Paper:

Coupled neutronics/thermal–hydraulics analysis of CANDU–SCWR fuel channel

Journal:

Annals of Nuclear Energy

Summary:

At supercritical pressure condition, the thermal–hydraulics behavior of water differs strongly from that at
sub-critical pressure due to a rapid variation of the thermal–physical properties across the pseudo-critical
line. A coupling analysis of neutronics and thermal–hydraulics has become important for SCWR,
because of the strong link between the water density and the neutron spectrum and subsequently the
power distribution. The neutronics code Monte Carlo N-Particle code (MCNP) and the subchannel code
Advanced Thermal–Hydraulics Analysis Subchannel (ATHAS) are used in a coupled way to better understand
the design characteristics of a pressure tube type SCWR fuel channel. The results show that: the
developed coupled code system can be used to analyze pressure tube type SCWR fuel bundles; improved
radial fuel enrichment profile will optimize the coolant and cladding temperature distribution to meet
the design criteria; smaller pressure tube pitch will result in more flatten axial power distribution and
more uniform radial power distribution.

Co-author:

Jianqiang Shan, Wei Chen, Bo Wook Rhee, Laurence K.H. Leung

Volume:

37 (2010)

Page Number:

58–65

Translation or Not:

No

Date of Publication:

2010-10-28