Published June 2022 | Version v1
Journal article

Benchmarking of the CUPID code to the ASSERT code in a CANDU channel

  • 1. Korea Atomic Energy Research Institute, Daejon (Korea, Republic of)
  • 2. Nuclear Engineering Service & Solution, Sejong (Korea, Republic of)
  • 3. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

The CUPID code was developed and is continuously updated in KAERI. Verification and validation (V&V) is mainly done for light water reactors (LWRs). This paper describes a benchmarking of the detailed mesh level compared with sub-channel level for application to pressurized heavy water reactors (PHWRs), even though component scale comparison for the PHWR moderator system was done once before. We completed a sub-channel level comparison between the CUPID code and the ASSERT code and a CUPID code analysis. Because the ASSERT code has already been validated with numerous experiments, benchmarking with the ASSERT code will offer us more trust on the CUPID code. The target channel has high power and thus high pressure deformation. The high power channel tends to have a high possibility of critical heat flux (CHF), because a high void fraction and quality in channel exit region appear. In this research, after determining the reference grid and T/H model, we compared the sub-channel level results of the CUPID code with those of the ASSERT code

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
54
Journal Issue
11
Journal Page Range
p. 4338-4347
ISSN
1738-5733

Optional Information

Notes
14 refs, 5 figs, 12 tabs