Published October 2013
| Version v1
Miscellaneous
Integrity evaluation of main piping system in a sodium test loop
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
In this study, integrity evaluations of the main piping system in the sodium test loop were conducted according to the design guidelines of the French RCC-MRx RB 3600 and ASME B31.1. The evaluation results according to the two design codes showed that the integrity of the main piping system was maintained under an intended steady state load condition. The sodium test loop of the STELLA (Sodium integral effect test loop for safety simulation and assessment)-1 is for component performance tests of heat exchangers and a mechanical pump. The large sodium test facility with a sodium inventory of 18 tons is intended for simulating the thermal hydraulic decay heat removal behavior of the Korean prototype Sodium-cooled Fast Reactor (SFR)
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS Fall meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2013 Fall meeting of the KNS
- Dates
- 23-25 Oct 2013
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 45082105
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; DESIGN; HEAT EXCHANGERS; PERFORMANCE TESTING; PIPES; PUMPS; SAFETY; TEST FACILITIES
- Descriptors DEC
- EQUIPMENT; REMOVAL; SIMULATION; TESTING; TUBES
Optional Information
- Notes
- 4 refs, 5 figs, 1 tab