Assessment of COMSOL capability to analyze thermal-hydraulic characteristics of Korean helium cooled test blanket
Creators
- 1. Department of Nuclear Engineering, Seoul National University, Daehak-dong, Gwanak-gu, Seoul 151-742 (Korea, Republic of)
- 2. Korea Atomic Energy Research Institute, Deokjin-dong, Yuseong-gu, Daejeon 305-600 (Korea, Republic of)
- 3. KEPCO International Nuclear Graduate School, Shinam-ri, 1456-1, Seosaeng-myeon, Ulju-gun, Ulsan 689-882 (Korea, Republic of)
Description
Highlights: ► Thermal-hydraulic analysis capability of the multi-physics code, COMSOL, was validated by the computational result of commercial CFD code, CFX-10. ► The design of the Korean helium cooled test blanket was selected as a reference model. ► Maximum deviation of peak temperature between two codes was below 1.5%. ► Although the COMSOL based on finite element method has a little numerical error in the fluid dynamic simulation, but the capability of COMSOL was acceptable generally. -- Abstract: Analyzing thermal hydraulic characteristics of the blanket is one of key factors for the blanket design. Since complicated phenomena in the blanket, especially a coupling effect between neutronics and heat transfers, make accurate analyses of the blanket very challenging. Therefore, advanced analysis method should be adopted to resolve the multi-physical problem. The present study uses COMSOL multi-physics code for thermal analyses of the blanket, since the COMSOL conceptually has sufficient capability of considering the heat transfer, neutronics, and even tritium behaviors together in a single code framework. As a part of this track, this study first validates the thermal-hydraulic analysis capability of the COMSOL by comparing with the CFD code, which can provide accurate thermal prediction for complicated single phase flow problems. This study selects KO HCML TBM as the reference blanket design for the validation because the detailed TBM design and preliminary analysis are available. Peak temperatures at the top and bottom region of TBM by COMSOL were 897.49 K and 882.69 K, respectively. The maximum deviation of peak temperature to the CFD result was below 1.5%. And the temperature distributions of two codes were overall similar to each other. Therefore, it is concluded that the COMSOL has an acceptable thermal-hydraulic analysis capability
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2013.02.016Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2013.02.016;
- PII
- S0920-3796(13)00130-0;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 88
- Journal Issue
- 9-10
- Journal Page Range
- p. 2240-2243
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 27. symposium on fusion technology
- Acronym
- SOFT-27
- Dates
- 24-28 Sep 2012
- Place
- Liege (Belgium)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45054008
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; FINITE ELEMENT METHOD; HEAT TRANSFER; HELIUM; PEAKS; SIMULATION; THERMAL ANALYSIS; THERMAL HYDRAULICS; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; ELEMENTS; ENERGY TRANSFER; FLUID MECHANICS; FLUIDS; GASES; HYDRAULICS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MATHEMATICAL SOLUTIONS; MECHANICS; NONMETALS; NUCLEI; NUMERICAL SOLUTION; ODD-EVEN NUCLEI; RADIOISOTOPES; RARE GASES; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.