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Transient Analysis of Natural Circulation Nuclear Reactor REX-10

Title
Transient Analysis of Natural Circulation Nuclear Reactor REX-10
Author
전규동
Keywords
SMR; SMART; REX-10; RTF; natural circulation; district heating reactor; scaling law; MARS code; once-through helical-coiled heat exchanger; integral-type reactor
Issue Date
2011-07
Publisher
TAYLOR & FRANCIS LTD, 4 PARK SQUARE, MILTON PARK, ABINGDON OX14 4RN, OXON, ENGLAND
Citation
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 권: 48 호: 7 페이지: 1046-1056
Abstract
As research regarding small- and medium-sized nuclear reactors (SMRs) has rapidly increased worldwide, the Regional Energy Research Institute for Next Generation (RERI) is designing a new conceptual nuclear reactor, called the Regional Energy rX-10MW(t) (REX-10). The REX-10 is an integral-type nuclear reactor and adopts natural circulation for heat removal. Since the REX-10 is designed for district heating and small-scale power generation near residential areas, it has to guarantee safety under all circumstances. Thus, the REX-10 Test Facility (RTF) is designed to evaluate the natural circulation behavior in the REX-10. On the basis of a theoretical model and reactor safety, two experimental parameters (heater power and feedwater flow rate) were chosen and various transient experiments are conducted. As a result of six transient experiments, the RTF guarantees safety against abrupt changes in the experimental parameters. Furthermore, all the experiments are simulated by using the MARS code. In most cases, the results of the MARS code show good agreement with the experimental results. However, in case of the chiller trip, the MARS code overestimates the temperature and generates a fluctuation of the primary flow. However, both results show a similar trend after the fluctuation is finished.
URI
http://www.tandfonline.com/doi/abs/10.1080/18811248.2011.9711789http://hdl.handle.net/20.500.11754/43875
ISSN
0022-3131; 1881-1248
DOI
10.1080/18811248.2011.9711789
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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