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Choi, Sungyeol
Nuclear Fuel Cycle Engineering Lab (NCEL)
Research Interests
  • Fuel Cycle Chemistry; Nuclear Plant Chemistry; Non-aqueous Electrochemistry; Nuclear Security

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PASCAR: Long burning small modular reactor based on natural circulation

Cited 13 times inthomson ciCited 17 times inthomson ci
Title
PASCAR: Long burning small modular reactor based on natural circulation
Author
Choi, SungyeolCho, Jae-HyunBae, Moo-HoonLim, JunPuspitarini, DinaJeun, Ji HoonJoo, Han-GyuHwang, Il Soon
Keywords
LEAD-BISMUTH; DESIGN; STEELS; CORROSION; FUEL; BEHAVIOR; COOLANT; SYSTEMS; PEACER
Issue Date
2011-05
Publisher
ELSEVIER SCIENCE SA
Citation
NUCLEAR ENGINEERING AND DESIGN, v.241, no.5, pp.1486 - 1499
Abstract
PASCAR is a 100 MWt/35 MWe lead-bismuth-cooled small modular reactor which requires no on-site refueling and well suits to be used as a distributed power source in either a single unit or a cluster for electricity, heat supply, and desalination. This paper includes both steady-state and transient performance evaluations for neutronics and thermal-hydraulics. Through design optimization studies for minimizing a burn-up reactivity loss, the metallic fuels-loaded core was designed with less than 1$ reactivity swing over 20-year cycle. A radial peaking power location shows the slow inward migration from outer enrichment zones while maintaining peaking factor within 1.35, reducing radiation damage and corrosion duty of high temperature environments. Equipped with coolant flow path large enough to ensure low pressure drop, this reactor is intended to operate by only natural circulation of chemically inert coolant within relatively low temperature range, 320-420 degrees C. Peak outlet temperature is nearly 450 degrees C where an Al-containing duplex cladding has sufficient corrosion resistance. Despite of 50% decrease of fuel thermal conductivity after swelling, inherent negative reactivity feedback and passive decay heat removal capability could secure an ample safety margin of peak fuel centerline temperature in tow safety analyses, unprotected transient overpower and unprotected loss of heat sink. The likelihood of loss of coolant, loss of flow, and local blockage is virtually eliminated by employing respectively a double-walled vessel, pump-less cooling, and cross-flow allowed open square assemblies. Simple fabrication, modular construction, and long burning cycle would compensate for economic disadvantages over smaller power and lower temperature than those of conventional fast reactors. (C) 2011 Elsevier B.V. All rights reserved
URI
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DOI
10.1016/j.nucengdes.2011.03.005
ISSN
0029-5493
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