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
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 55095373
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- A CODES; BENCHMARKS; C CODES; CANDU TYPE REACTORS; DEFORMATION; FUEL CHANNELS; HEAT FLUX; HEAVY WATER COOLED REACTORS; MODERATORS; VOID FRACTION; WATER COOLED REACTORS
- Descriptors DEC
- COMPUTER CODES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 14 refs, 5 figs, 12 tabs