Improved PWR Core Characteristics with Thorium-containing Fuel

作者: Cheuk Wah Lau

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摘要: Thorium is an element for possible use as nuclear fuel, because of the fertile property Th-232, which could convert into U-233 after neutron capture and beta decays. However, thorium based fuels have not been successfully implemented, high cost higher complexity compared with once-through uranium fuel. Therefore, focus this thesis on in traditional light water reactors improving core characteristics by: achieving a more homogenous power distribution to provide larger thermal margins, plutonium incineration efficiency reduce stockpile, improved load-following capacity. The chosen methodology similar one commonly used industry. The model Ringhals-3 PWR, Studsvik Scandpower Ltd. codes are calculate neutronics fuel reactor cores. The divided three parts. first part addresses absorber concept, achieved by adding small amounts pellets improve margins. benefits reduced need burnable absorbers, slower decrease reactivity function burnup. The second describes thorium-plutonium mixed oxide since barely generates any new uranium-plutonium cores alter behavior such stronger Doppler feedback lower fraction delayed neutrons, require boron (B-10) enrichment, increased number control rods efficiency. The third focusing capacity thorium-containing Th-232 has about times absorption cross section U-238, hardens spectrum. This leads less sensitivity spectrum changes, xenon poisoning, axial fluctuations upon load changes. capacity, be positive complement intermittent sources, solar or wind power.

参考文章(35)
D McEachern, Deep-Burn Modular Helium Reactor Fuel Development Plan Office of Scientific and Technical Information (OSTI). ,(2002) , 10.2172/885771
SG Popov, Juan J Carbajo, G Yoder, Thermophysical Properties of MOX and UO2 Fuels Including the Effects of Irradiation Other Information: PBD: 11 Jan 2001. ,(2001) , 10.2172/777671
A. M. Christie, C. G. Poncelet, On the Control of Spatial Xenon Oscillations Nuclear Science and Engineering. ,vol. 51, pp. 10- 24 ,(1973) , 10.13182/NSE73-A23253
D.A. Nitti, E.C. Moncrief, C.A. Burkart, THORIUM FUEL SEPARATION ENGINEERING STUDIES. ,(1968)
Sidik Permana, Hiroshi Sekimoto, Naoyuki Takaki, Feasibility of Water Cooled Thorium Breeder Reactor Based on LWR Technology American Nuclear Society - ANS, La Grange Park (United States). ,(2007)
Henrik Nylén, Joerg Marten, Jenny Roudén, Urban Sandberg, Pål Efsing, Shielding fuel assemblies used to protect the beltline weld of the reactor pressure vessel from fast neutron radiation in Ringhals unit 3 and 4 International Conference on the Physics of Reactors 2010, PHYSOR 2010, Pittsburgh, PA, United States, 9 May 2010 through 14 May 2010. pp. 1534- 1540 ,(2010)
Materials Section, Thorium fuel cycle : potential benefits and challenges International Atomic Energy Agency. ,(2005)
Michael Todosow, A. Galperin, S. Herring, M. Kazimi, T. Downar, A. Morozov, Use of Thorium in Light Water Reactors Nuclear Technology. ,vol. 151, pp. 168- 176 ,(2005) , 10.13182/NT151-168
Jae Ho Yang, Ki Won Kang, Kun Woo Song, Chan Bock Lee, Youn Ho Jung, Fabrication and thermal conductivity of (Th, U)O2 pellets Nuclear Technology. ,vol. 147, pp. 113- 119 ,(2004) , 10.13182/NT04-A3518
Kevan D. Weaver, J. Stephen Herring, Performance of Thorium-Based Mixed-Oxide Fuels for the Consumption of Plutonium in Current and Advanced Reactors Nuclear Technology. ,vol. 143, pp. 22- 36 ,(2003) , 10.13182/NT03-A3395