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Validation Calculations for the Application of MARS Code to the Safety Analysis of Research Reactors
Park, Cheol; Kim, H.; Chae, H. T.; Lim, I. C.
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2006
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2006
AbstractAbstract
[en] In order to investigate the applicability of MARS code to the accident analysis of the HANARO and other RRs, the following test data were simulated. Test data of the HANARO design and operation, Test data of flow instability and void fraction from published documents, IAEA RR transient data in TECDOC-643, Brazilian IEA-R1 experimental data. For the simulation of the HANARO data with finned rod type fuels at low pressure and low temperature conditions, MARS code, developed for the transient analysis of power reactors, was modified. Its prediction capability was assessed against the experimental data for the HANARO. From the assessment results, it can be said that the modified MARS code could be used for analyzing the thermal hydraulic transient of the HANARO. Some other simulations such as flow instability test and reactor transients were also done for the application of MARS code to RRs with plate type fuels. In the simulation for these cases, no modification was made. The results of simulated cases show that the MARS code can be used to the transient analysis of RRs with careful considerations. In particular, it seems that an improvement on a void model may be necessary for dealing with the phenomena in high void conditions
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Source
Oct 2006; 36 p; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); 18 refs, 29 figs, 7 tabs
Record Type
Report
Literature Type
Numerical Data
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COMPUTER CODES, DATA, ENRICHED URANIUM REACTORS, FLUID MECHANICS, HYDRAULICS, INFORMATION, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MATERIALS TESTING REACTORS, MECHANICS, NUMERICAL DATA, OPERATION, POOL TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TEST FACILITIES, TEST REACTORS, TESTING, WATER COOLED REACTORS, WATER MODERATED REACTORS
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