Preliminary conceptual design of a small high-flux multi-purpose LBE cooled fast reactor
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
The design concept of a Small High-flux Multipurpose LBE(Lead Bismuth Eutectic) cooled Fast Reactor (SHMLFR) was proposed in the paper. The primary cooling system of the reactor is forced circulation, and the fuel element form is arc-plate loaded high enrichment MOX fuel. The core is cylindrical with a flux trap set in the center of the core, which can be used as an irradiation channel. According to the requirements of the core physical design, a series of physical design criteria and constraints were given, and the steady and transient parameters of the reactor were calculated and analyzed. Regarding the thermal and hydraulic phenomena of the reactor, a simplified model was used to conduct a preliminary analysis of the fuel plates at special positions, and the temperature field distribution of the fuel plate with the highest power density under different coolant flow rates was simulated. The results show that the various parameters of SHMLFR meet the requirements and design criteria of the physical design of the core and the thermal design of the reactor. This implies that the conceptual design of SHMLFR is feasible
Abstract
The design concept of a Small High-flux Multipurpose LBE(Lead Bismuth Eutectic) cooled Fast Reactor (SHMLFR) was proposed in the paper. The primary cooling system of the reactor is forced circulation, and the fuel element form is arc-plate loaded high enrichment MOX fuel. The core is cylindrical with a flux trap set in the center of the core, which can be used as an irradiation channel. According to the requirements of the core physical design, a series of physical design criteria and constraints were given, and the steady and transient parameters of the reactor were calculated and analyzed. Regarding the thermal and hydraulic phenomena of the reactor, a simplified model was used to conduct a preliminary analysis of the fuel plates at special positions, and the temperature field distribution of the fuel plate with the highest power density under different coolant flow rates was simulated. The results show that the various parameters of SHMLFR meet the requirements and design criteria of the physical design of the core and the thermal design of the reactor. This implies that the conceptual design of SHMLFR is feasible
참고문헌 (20)
- A. V. Zrodnikov, "Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75", 100, 2005, pp.236, 1490~1502
- C. F. Smith, "SSTAR : the US lead-cooled fast reactor(LFR)", J. Nucl. Mater, 376, pp.255~259 (2008)
- S. Bortot, "Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator", Nucl. Eng. Des, 241, pp.3021~3031 (2011)
- S. Choi, "PASCAR : long burning small modular reactor based on natural circulation", Nucl. Eng. Des, 241, pp.1486~1499 (2011)
- A. Frogheri, "The advanced lead fast reactor European demonstrator (ALFRED)", The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics (2013)
- H. Chen, "Conceptual design of a small modular natural circulation lead cooled fast reactor SNCLFR-100", Int. J. Hydrogen Energy, 41, pp.7158~7168 (2016)
- R. D. Cheverton, "HFIR CORE NUCLEAR DESIGN", ~ (1971)
- Missouri University Research Reactor (MURR) Safety Analysis Report, "J. C. McKibben", ~ (2006)
- A. Roehrmoser, "Core model of new German neutron source FRM II", Nucl. Eng. Des, 240, pp.1417~1432 (2010)
- F. Diego, "Full 3-D core calculations with refueling for the OPAL research reactor using Monte Carlo code serpent 2", Ann. Nucl. Energy, 92, pp.369~377 (2016)
- J. Stillman, "Conceptual Design Parameters for MURR LEU U-Mo Fuel Conversion Design Demonstration Experiment", ~
- Y. H. Shin, "Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation", Prog. Nucl. Energy, 83, pp.433~442 (2015)
- H. Li, "Corrosion resistance in Pb-Bi alloy of 15-15Ti steel coated with Al 2 O 3", SiC bilayer thin films by magnetron sputtering, 2017, pp.125, 384~390
- G. Mckinney, "MCNP6 User's Manual - Version 1.0", ~ (2013)
- Lijian Rong, "Handbook of Lead and Lead-bismuth Eutectic Alloys" (2014), science press
- Thermophysical Properties of MOX and UO2 Fuels Including the Effects of Irradiation, "S. G. Popov", office of scientific &technical information, ~ (2001)
- K. Haarmann, "The T91", P91 Book, 2008
- Chunsuo Xin, "Study on methods for Improving surface temperature uniformity of Low thermal conductivity materials", Aero. Metrol. Technol, pp.31~35 (2013)
- Material Property Correlations: Comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO, "W. G. Luscher", office of scientific &technical information, ~ (2015)
- Y. Zhang, "Review of thermalhydraulic issues and studies of lead-based fast reactors", Renew. Sustain. Energy Rev, 120 (2020)
