Published 2008 | Version v1
Miscellaneous

Effects of pressure condition for LOCA acceleration test profile on equipment integrity

  • 1. Center for Nuclear Equipment and Machinery, Korea Inst. of Machinery and Materials, Daejeon (Korea, Republic of)
  • 2. Kurume National College of Technology, Dept. of Mechanical Engineering, Kurume, Fukuoka (Korea, Republic of)

Description

All equipment related to safety in nuclear power plants must perform their safety functions under defined condition, including postulated DBA condition as well as normal environmental condition. LOCA (Loss of Coolant Accident) of the DBA is the severest condition of high temperature, high pressure and sprayed chemicals during approximately 6 months. Since the perfect qualification of equipment in such LOCA test requires a long time and highly reliable test facility, the realistic LOCA simulation test for equipment qualification is performed with modified shortened test profile enveloping temperature and pressure condition of specific NPP. The detailed process for modification of this LOCA test profile are proposed by Park et al. (2006), based on the Arrhenius equation. However, the shortened test profile may cause quite unfavorable effects on equipment integrity during and after LOCA test. In this paper, we have found that failure possibility of limit switch during LOCA test may be greatly increased due to elevated test pressure in the modified test profile. Therefore, we suggest the refined modification method of LOCA test profile, which is applicable for pressure-vulnerable equipment. (author)

Part of:
NTHAS6: Proceedings of the 6th Japan-Korea symposium on nuclear thermal hydraulics and safety

Additional details

Publishing Information

Imprint Title
NTHAS6: Proceedings of the 6th Japan-Korea symposium on nuclear thermal hydraulics and safety
Imprint Pagination
818 p.
Journal Page Range
[4 p.]

Conference

Title
6. Japan-Korea symposium on nuclear thermal hydraulics and safety
Acronym
NTHAS6
Dates
24-27 Nov 2008
Place
Nago, Okinawa (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
43008065
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCELERATION; ARRHENIUS EQUATION; DESIGN BASIS ACCIDENTS; FAILURES; LOSS OF COOLANT; NUCLEAR POWER PLANTS; SAFETY; SWITCHES; TESTING
Descriptors DEC
ACCIDENTS; ELECTRICAL EQUIPMENT; EQUATIONS; EQUIPMENT; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; THERMAL POWER PLANTS

Optional Information

Notes
This USB flash memory can be used for WINDOWS 2000/XP, MACINTOSH 9.x/10.x; Acrobat Reader is included; Data in PDF format, Folder Name: FullPaper, Paper ID: N6P1056.pdf; 9 refs., 7 figs., 3 tabs.