Published October 2014 | Version v1
Miscellaneous

Comparison of SBLOCA Test Results with the FESTA Facility for the SMART Design

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

The FESTA facility is a full height, 1/49-volume scaled test facility with four trains of a secondary system and PRHRS, and can be used to investigate the integral performance of the interconnected components and possible thermal-hydraulic phenomena occurring in the SMART (System-Integrated Modular Advanced Reactor) design, and to validate its safety for various design basis accidents and broad transient scenarios. The role of FESTA can be extended to examine and verify the normal, abnormal, and emergency operating procedures required during the construction phases of SMART. During the design of the FESTA facility, the height is preserved to the full scale, and its area and volume are scaled down to 1/49 compared with the prototype plant, SMART. The scaling ratios adopted in FESTA with respect to SMART are summarized in Table 1. The maximum core power is 2..0 MW, which is about 30% of the scaled full power. The design pressure and temperature of SMART-ITL can simulate the maximum operating conditions, that is, 18.0 MPa and 350 .deg. C. A preliminary analysis of small-break loss of coolant accident (SBLOCA) tests using the MARS/KS code for FESTA was previously conducted. In addition, major test results of SBLOCA scenarios with the VISTA-ITL facility for the SMART design were discussed. In this research, three SBLOCA experimental tests of a safety injection system (SIS) line break, shutdown cooling system (SCS) line break and pressurizer safety valve (PSV) line break for the SMART design were successfully performed and its major results have been compared and discussed. An integral effect test has been performed for the SBLOCA scenario for the SMART design with the FESTA facility

Part of:
Proceedings of the KNS 2014 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2014 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[4 p.]

Conference

Title
2014 Fall Meeting of the KNS
Dates
29-31 Oct 2014
Place
Pyongchang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
46060778
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AFTER-HEAT; LOSS OF COOLANT; NATURAL CONVECTION; PERFORMANCE; TEST FACILITIES; THERMAL ANALYSIS
Descriptors DEC
ACCIDENTS; CONVECTION; ENERGY TRANSFER; HEAT TRANSFER; MASS TRANSFER; REACTOR ACCIDENTS

Optional Information

Notes
4 refs, 2 figs, 3 tabs