Optimization of a Seed and Blanket Thorium-uranium Fuel Cycle for Pressurized Water Reactors PDF Download
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Author: Dean Wang Publisher: ISBN: Category : Languages : en Pages : 252
Book Description
(Cont.) Fuel performance was analyzed using FRAPCON. The radioactivity and decay heat from the spent seed and blanket fuel were studied using MIT's MCODE (which couples MCNP and ORIGEN) to do depletion calculations, and ORIGEN to analyze the spent fuel characteristics after discharge. The analyses show that the WASB core can satisfy the requirements of fuel cycle length and safety margins of conventional PWRs. The coefficients of reactivity are comparable to currently operating PWRs. However, the reduction in effective delayed neutron fraction (eff) requires careful review of the control systems because of its importance to short term power transients. Whole core analyses show that the total control rod worth of the WASB core is about 1/3 less than those of a typical PWR for a standard arrangement of Ag-In-Cd control rods in the core. The use of enriched boron in the control rods can effectively improve the control rod worth. The control rods have higher worth in the seed than in the blanket. Therefore, a new loading pattern has been designed so that almost all the control rods will be located in seed assemblies. However, the new pattern requires a redesign of the vessel head of the reactor, which is an added cost in case of retrofitting in existing PWRs. Though the WASB core has high power peaking factors, acceptable MDNBR in the core can be achieved under conservative assumptions by using grids with large local pressure loss coefficient in the blanket. However, the core pressure drop will increase by 70% ...
Author: Dean Wang Publisher: ISBN: Category : Languages : en Pages : 252
Book Description
(Cont.) Fuel performance was analyzed using FRAPCON. The radioactivity and decay heat from the spent seed and blanket fuel were studied using MIT's MCODE (which couples MCNP and ORIGEN) to do depletion calculations, and ORIGEN to analyze the spent fuel characteristics after discharge. The analyses show that the WASB core can satisfy the requirements of fuel cycle length and safety margins of conventional PWRs. The coefficients of reactivity are comparable to currently operating PWRs. However, the reduction in effective delayed neutron fraction (eff) requires careful review of the control systems because of its importance to short term power transients. Whole core analyses show that the total control rod worth of the WASB core is about 1/3 less than those of a typical PWR for a standard arrangement of Ag-In-Cd control rods in the core. The use of enriched boron in the control rods can effectively improve the control rod worth. The control rods have higher worth in the seed than in the blanket. Therefore, a new loading pattern has been designed so that almost all the control rods will be located in seed assemblies. However, the new pattern requires a redesign of the vessel head of the reactor, which is an added cost in case of retrofitting in existing PWRs. Though the WASB core has high power peaking factors, acceptable MDNBR in the core can be achieved under conservative assumptions by using grids with large local pressure loss coefficient in the blanket. However, the core pressure drop will increase by 70% ...
Author: Fouad Sabry Publisher: One Billion Knowledgeable ISBN: Category : Science Languages : en Pages : 530
Book Description
What Is Thorium Fuel Cycle The fertile material in the thorium fuel cycle is an isotope of thorium called 232Th, and the thorium fuel cycle itself is a kind of nuclear fuel cycle. Within the reactor, 232Th is converted into the fissile artificial uranium isotope 233U, which is then used as the fuel for the nuclear reactor. Natural thorium, in contrast to natural uranium, only contains minute quantities of fissile material, which is insufficient to kick off a nuclear chain reaction. In order to kickstart the fuel cycle, either more fissile material or an other neutron source is required. 233U is created when 232Th, which is powered by thorium, absorbs neutrons in a reactor. This is analogous to the process that occurs in uranium breeder reactors, in which fertile 238U is subjected to neutron absorption in order to produce fissile 239Pu. The produced 233U either fissions in situ or is chemically removed from the old nuclear fuel and converted into new nuclear fuel, depending on the architecture of the reactor and the fuel cycle. Fissioning in situ is the more efficient method. How You Will Benefit (I) Insights, and validations about the following topics: Chapter 1: Thorium fuel cycle Chapter 2: Nuclear reactor Chapter 3: Radioactive waste Chapter 4: Fissile material Chapter 5: Nuclear fuel cycle Chapter 6: MOX fuel Chapter 7: Breeder reactor Chapter 8: Uranium-238 Chapter 9: Energy amplifier Chapter 10: Subcritical reactor Chapter 11: Integral fast reactor Chapter 12: Fertile material Chapter 13: Uranium-233 Chapter 14: Plutonium-239 Chapter 15: Isotopes of uranium Chapter 16: Isotopes of plutonium Chapter 17: Weapons-grade nuclear material Chapter 18: Uranium-236 Chapter 19: Burnup Chapter 20: Liquid fluoride thorium reactor Chapter 21: Nuclear transmutation (II) Answering the public top questions about thorium fuel cycle. (III) Real world examples for the usage of thorium fuel cycle in many fields. (IV) 17 appendices to explain, briefly, 266 emerging technologies in each industry to have 360-degree full understanding of thorium fuel cycle' technologies. Who This Book Is For Professionals, undergraduate and graduate students, enthusiasts, hobbyists, and those who want to go beyond basic knowledge or information for any kind of thorium fuel cycle.
Author: Dean Wang
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