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)

Part of:
Proceedings of the KNS Fall meeting

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