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Author: Charles P. Kliewer Publisher: ISBN: Category : Nuclear reactors Languages : en Pages : 320
Book Description
A significant amount of interest has been aroused recently concerning the advancement of the current pressurized water reactor core designs with a special emphasis towards improving the conversion characteristics of these reactors. Most reports have been divided into two camps; those that deal with the neutronic aspects and those that deal with the thersohydraulic concerns. Seldom do these two areas get combined for purposes of evaluating a new design. In this effort, the author takes a pragmatic approach to this area in so far as looking into ways of incorporating this advanced technology into current operational power plants. In so doing the Trojan Nuclear Power Plant was selected to serve as the reference design plant. This was done since it is a Westinghouse designed reactor, as are a large portion of the PWR's in the United States, and because it has one of the largest thermal power ratings in the nation as well. Both neutronic and thermohydraulic aspects are examined as well as an alternative fuel concept. In order to carry out the analysis computer codes COBRA-IV and LEOPARD were employed on a CYBER 170/710 mainframe computer. COBRA-IV was used to obtain results relating to the associated pressure loss and core temperature characteristics while LEOPARD was used for the neutronic aspects. A parametric study was initiated using fuel enrichment and pitch as the variables that would be systematically changed. As an additional factor to assure cross compatibility, the fuel rod diameter was held to a constant value throughout this analysis. Results of this research strongly indicate that current operational power plants can be effectively altered to become converters or low level breeders with only configurational changes in the core itself and no major equipment changes. Hence the author concludes that this concept is both feasible and readily attainable with the current level of technology. An additional benefit that would be realized under the adoption of this design would be the marked improvement in the utilization of uranium ore which ultimately becomes fuel. This would directly result in the extension of the power generation capability associated with nuclear power well into the next century.
Author: Charles P. Kliewer Publisher: ISBN: Category : Nuclear reactors Languages : en Pages : 320
Book Description
A significant amount of interest has been aroused recently concerning the advancement of the current pressurized water reactor core designs with a special emphasis towards improving the conversion characteristics of these reactors. Most reports have been divided into two camps; those that deal with the neutronic aspects and those that deal with the thersohydraulic concerns. Seldom do these two areas get combined for purposes of evaluating a new design. In this effort, the author takes a pragmatic approach to this area in so far as looking into ways of incorporating this advanced technology into current operational power plants. In so doing the Trojan Nuclear Power Plant was selected to serve as the reference design plant. This was done since it is a Westinghouse designed reactor, as are a large portion of the PWR's in the United States, and because it has one of the largest thermal power ratings in the nation as well. Both neutronic and thermohydraulic aspects are examined as well as an alternative fuel concept. In order to carry out the analysis computer codes COBRA-IV and LEOPARD were employed on a CYBER 170/710 mainframe computer. COBRA-IV was used to obtain results relating to the associated pressure loss and core temperature characteristics while LEOPARD was used for the neutronic aspects. A parametric study was initiated using fuel enrichment and pitch as the variables that would be systematically changed. As an additional factor to assure cross compatibility, the fuel rod diameter was held to a constant value throughout this analysis. Results of this research strongly indicate that current operational power plants can be effectively altered to become converters or low level breeders with only configurational changes in the core itself and no major equipment changes. Hence the author concludes that this concept is both feasible and readily attainable with the current level of technology. An additional benefit that would be realized under the adoption of this design would be the marked improvement in the utilization of uranium ore which ultimately becomes fuel. This would directly result in the extension of the power generation capability associated with nuclear power well into the next century.
Author: Yigal Ronen Publisher: CRC Press ISBN: 9780849360817 Category : Technology & Engineering Languages : en Pages : 282
Book Description
The purpose of this book is to describe concepts related to advanced water reactors, with particular focus on Advanced Pressurized Water Reactors. It discusses the severe disadvantages which water reactors have with respect to uranium utilization. It also reveals new concepts in which the conversion ratio and the uranium utilization is improved. This interesting work includes information on various others ways used in addition to the increase in the conversion ratio. This is an informative, useful book for all nuclear scientists and engineers, and anyone who is interested in high converting water reactors.
Author: Wade H. Shafer Publisher: Springer Science & Business Media ISBN: 1461305993 Category : Science Languages : en Pages : 411
Book Description
Masters Theses in the Pure and Applied Sciences was first conceived, published, and disseminated by the Center for Information and Numerical Data Analysis and Synthesis (CINDAS) * at Purdue University in 1 957, starting its coverage of theses with the academic year 1955. Beginning with Volume 13, the printing and dissemination phases of the activity were transferred to University Microfilms/Xerox of Ann Arbor, Michigan, with the thought that such an arrangement would be more beneficial to the academic and general scientific and technical community. After five years of this joint undertaking we had concluded that it was in the interest of all con cerned if the printing and distribution of the volumes were handled by an interna tional publishing house to assure improved service and broader dissemination. Hence, starting with Volume 18, Masters Theses in the Pure and Applied Sciences has been disseminated on a worldwide basis by Plenum Publishing Cor poration of New York, and in the same year the coverage was broadened to include Canadian universities. All back issues can also be ordered from Plenum. We have reported in Volume 32 (thesis year 1987) a total of 12,483 theses titles from 22 Canadian and 176 United States universities. We are sure that this broader base for these titles reported will greatly enhance the value of this important annual reference work. While Volume 32 reports theses submitted in 1987, on occasion, certain univer sities do report theses submitted in previous years but not reported at the time.
Author: Bo Feng (Ph. D.) Publisher: ISBN: Category : Languages : en Pages : 269
Book Description
This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using nitride fuel in place of oxides in Pu-based high conversion light water reactor designs. Using the higher density nitride fuel hardens the neutron energy spectrum and results in higher breeding ratios. The state-of-the-art high conversion light water reactor, the Resource-renewable Boiling Water Reactor (RBWR), served as the template core upon which comparative studies between nitride and oxide fuels were performed. A 1/3 core reactor physics model was developed for the RBWR using the stochastic transport code MCNP. The code was coupled with a lumped channel thermalhydraulics 5-channel model for steady-state analyses. The depletion code MCODE, which links MCNP with ORIGEN, was used for all burnup calculations. Select physics parameters were calculated and with the exception of the void coefficients, agreed with reported data. The void coefficients of the coupled core were calculated to be slightly positive using two different methods (10% power increase and 5% flow reduction). The standard RBWR assembly designs, which use tight lattice hexagonal fuel rod arrays, with oxide fuel were then replaced with various nitride fuel assembly designs to determine the potential increase in breeding ratio, the potential to breed with pressurized water, and the potential to improve the critical power ratio with a wider pin pitch. Without changing the assembly geometry or discharge burnup, using nitride fuel resulted in a breeding ratio of 1.14. Using single-phase liquid water, the nitride fuel RBWR assembly resulted in a conversion ratio of 1.00. Another nitride fuel assembly design with boiling water maintained a 1.04 breeding ratio while increasing the pitch-todiameter ratio from 1.13 to 1.20. This modification increased the hot assembly critical power ratio from 1.22 to 1.36, as calculated using the Liu-2007 correlation. A high-porosity nitride fuel is recommended for high burnup conditions, to accommodate the nitride fuel's higher swelling and less favorable mechanical properties compared to the oxide fuel. The high porosity allows additional volume for pressure-induced densification, alleviating swelling and subsequent cladding strain. To predict the performance of high-porosity nitride fuel, fission gas and fuel behavior mechanistic models were developed for high burnup and low-temperature conditions. These models were validated with reported irradiation data and implemented, along with fuel material properties, into the steady-state fuel behavior code FRAPCON-EP. Under simulated RBWR conditions, a fuel density no more than 85% of theoretical density is recommended to maintain satisfactory fuel performance.
Author: Publisher: ISBN: Category : Pressurized water reactors Languages : en Pages : 48
Book Description
A total of 193 annotated references to unclassified reports on the design, development and construction of the Shippingport Pressurized Water Reactor is presented. Author, subject, and report number indexes are included.
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Author: Charles P. Kliewer
Author: Yigal Ronen
Author: Wade H. Shafer
Author: Robert Joseph Florian
Author: Charles Francis Bonilla
Author: Bo Feng (Ph. D.)
Author: U.S. Atomic Energy Commission. Division of Reactor Development
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