ESBWR passive safety system performance under loss of coolant accidents
- 1. Department of Nuclear Engineering, Faculty of Engineering, Chulalongkorn University, Wangmai, Patumwan, Bangkok, 10330 (Thailand)
- 2. School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017 (United States)
Description
Highlights: • The capability of the passive safety system in the advanced boiling water reactor is investigated. • The LOCAs tests results performed at PUMA-E integral test facility is summarized. • The performance of the GDCS, ICS, and PCCS responded to each case of LOCAs tests is compared. - Abstract: Several passive safety systems are included in the design of the Economic Simplified Boiling Water Reactor (ESBWR) safety system. To investigate the capability of the ESBWR passive safety system, the integral facility designed for ESBWR was applied to perform a series of experiments simulating Loss of Coolant Accidents (LOCAs) break events of the ESBWR. This paper is intended to summarize the LOCAs test results performed at the Purdue University Multi-Dimensional Integral Test Assembly for ESBWR application (PUMA-E) facility, namely, the Main Steam Line Break (MSLB), Bottom Drain Line Break (BDLB), Feed Water Line Break (FWLB) and Gravity Drain Line Break (GDLB). Furthermore, this study focuses on the comparison of important parameters in the main components such as Reactor Pressure Vessel (RPV), Containment, and Suppression Pool (SP) of the integral facility for those types of the LOCAs tests in three different phases of LOCAs, namely, the blowdown phase, Gravity Driven Coolant System (GDCS) period and long term cooling PCCS period. The various responses of passive safety function by GDCS, Isolation Coolant System (ICS), and Passive Containment Coolant System (PCCS) at the three different phases of LOCAs to the four types of the LOCAs tests are discussed and analyzed.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2016.12.005Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2016.12.005;
- PII
- S0149197016302761;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 96
- Journal Page Range
- p. 1-17
- ISSN
- 0149-1970
- CODEN
- PNENDE
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50068625
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COOLING SYSTEMS; FUEL STORAGE POOLS; LOSS OF COOLANT; PERFORMANCE; PRESSURE VESSELS; REACTIVITY; REACTOR SAFETY; SPENT FUEL STORAGE; STEAM LINE BREAK ACCIDENTS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; STORAGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.