Download or read book Neutronic Analysis of a Proposed Plutonium Recycle Assembly written by George Michael Solan and published by . This book was released on 1975 with total page 602 pages. Available in PDF, EPUB and Kindle. Book excerpt: A method for the neutronic analysis of plutonium recycle assemblies has been developed with emphasis on relative power distribution prediction in the boundary area of vastly different spectral regions. Such regions are those of mixed oxide (Pu0 2 in natural U02 ) fuel pins relative to enriched uranium pins, or water regions relative to fuel pin regions. The basic analytical methods for determination of spectrum averaged constants are given in the following descriptions: (1) Generalized Mixed Number Density (GMND) group constants (based on Breen's Mixed Number Density Method) are generated by a modified version of the spectrum code LASER, called LASER-M. (2) THERMOS Corrected LASER-M (TCL) group constants are based on mixed oxide- uranium oxide and water region boundary modeling in one dimensional (slab) geometry with the integral transport code THERMOS. The LASER-M model, as modified by addition of ENDF/B-II thermal cross sections for the plutonium isotopes, is used to predict the criticality of experimental lattices of U02 - 2 w/o Pu0 2, and fair agreement is shown. LASER-M unit cell depletion calculations with Yankee Core I data (3.4 w/o U-235) to 40,000 MWD/MT and Saxton Core II data (6.6 w/o Pu02 in natural U02) to 20,000 MWD/MT show good isotopic agreement. Saxton Critical Reactor Experiment (CRX) lattice cores (19 x 19 rod array) consisting of a single fuel type region (mixed oxide or uranium oxide) or multiregions of both pin types were analyzed for relative power distribution comparisons. Cores with water slot regions were included. LASER-M Normal, LASER-M GMND and TCL two group constants were used with PDQ-7 in the calculations. GMND results were in excellent agreement compared to the good agreement of TCL for these cases of isolated spectral disturbances in an asymptotic core region. The methods were applied to a proposed plutonium recycle "island design" assembly in which a large control rod water region is in close proximity to a zoned mixed oxide region. The TCL method yielded significantly greater power peaking and mixed oxide region average power owing to the spectral influence of the water region explicitly accounted for in this method. Such a result is consistent with published calculations. It is concluded that infinite lattice spectrum calculations are insufficient to deal with spectrum effects more complex than those in the Saxton CRX experiments.
Download or read book An Analysis of Plutonium Recycle Fuel Elements in San Onofre 1 written by Bruce William Foster Momsen and published by . This book was released on 1974 with total page 450 pages. Available in PDF, EPUB and Kindle. Book excerpt: A method has been developed to allow independent assessment of the use of plutonium recycle assemblies in operating reactors. This method utilizes Generalized Mixed Number Density (GMND) cross sections (based on Breen's Mixed Number Density cross sections) and the spectrum code LASER. LASER is modified to form LASER-M by adding ENDF/B-II thermal cross sections for the plutonium isotopes; adding edits to output G-aND cross sections, approximate microscopic removal and transport cross sections; and increasing LASERs compatibility with commonly used diffusion theory codes such as PDQ. Plutonium critical experiments for a number of lattices of 1.5 w/o and 6.6 w/o plutonium are analysed with LASER-M which is found to give better criticality agreement than LASER (without the ENDF/B-II plutonium cross sections) and other published data. Unit assembly power distributions are calculated for a uranium assembly and a constant and graded enrichment plutonium assembly both surrounded by uranium assemblies. The use of LASER-M with GMND cross sections is found to give excellent agreement with the published calculations of power distributions for the uranium assembly and good agreement for the plutonium assemblies. A quarter core depletion calculation of the San Onofre reactor containing four plutonium recycle demonstration assemblies is performed using the diffusion theory computer code PDQ-7. Use of PDQ-7 with GMND cross sections from LASER-M is shown to give excellent agreement with quasi experimental power distributions at cycle burnups of 0 MWD/MTM, 3342 MWD/MTM, and 6045 MWD/'MTM. Also, the calculated value of k-eff versus cycle burnup is determined to be in excellent agreement with the actual operating condition of k-eff = 1 .000.
Download or read book Plutonium Recycle Critical Facility Final Safeguards Analysis written by F. Swanberg and published by . This book was released on 1964 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics of Plutonium Recycling Issues and perspectives written by NEA Nuclear Science Committee. Working Party on Physics of Plutonium Recycling and published by Nuclear and Dev. This book was released on 1995 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt: On cover & title page: OECD Documents
Download or read book Neutronic Study of the Mono recycling of Americum in PWR and of the Core Conversion INMNSR Using the MURE Code written by Robert Sogbadji and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The MURE code is based on the coupling of a Monte Carlo static code and the calculation of the evolution of the fuel during irradiation and cooling periods. The MURE code has been used to analyse two different questions, concerning the mono-recycling of Am in present French Pressurized Water Reactor, and the conversion of high enriched uranium (HEU) used in the Miniature Neutron Source Reactor in Ghana into low enriched uranium (LEU) due to proliferation resistance issues. In both cases, a detailed comparison is made on burnup and the induced radiotoxicity of waste or spent fuel. The UOX fuel assembly, as in the open cycle system, was designed to reach a burn-up of 46GWd/T and 68GWd/T. The spent UOX was reprocessed to fabricate MOX assemblies, by the extraction of Plutonium and addition of depleted Uranium to reach burn-ups of 46GWd/T and 68GWd/T, taking into account various cooling times of the spent UOX assembly in the repository. The effect of cooling time on burnup and radiotoxicity was then ascertained. Spent UOX fuel, after 30 years of cooling in the repository required higher concentration of Pu to be reprocessed into a MOX fuel due to the decay of Pu-241. Americium, with a mean half-life of 432 years, has high radiotoxic level, high mid-term residual heat and a precursor for other long lived isotope. An innovative strategy consists of reprocessing not only the plutonium from the UOX spent fuel but also the americium isotopes which dominate the radiotoxicity of present waste. The mono-recycling of Am is not a definitive solution because the once-through MOX cycle transmutation of Am in a PWR is not enough to destroy all the Am. The main objective is to propose a “waiting strategy” for both Am and Pu in the spent fuel so that they can be made available for further transmutation strategies. The MOXAm (MOX and Americium isotopes) fuel was fabricated to see the effect of americium in MOX fuel on the burn-up, neutronic behavior and on radiotoxicity. The MOXAm fuel showed relatively good indicators both on burnup and on radiotoxicity. A 68GWd/T MOX assembly produced from a reprocessed spent 46GWd/T UOX assembly showed a decrease in radiotoxicity as compared to the open cycle. All fuel types understudy in the PWR cycle showed good safety inherent feature with the exception of the some MOXAm assemblies which have a positive void coefficient in specific configurations, which could not be consistent with safety features. The core lifetimes of the current operating 90.2% HEU UAl fuel and the proposed 12.5% LEU UOX fuel of the MNSR were investigated using MURE code. Even though LEU core has a longer core life due to its higher core loading and low rate of uranium consumption, the LEU core will have it first beryllium top up to compensate for reactivity at earlier time than the HEU core. The HEU and LEU cores of the MNSR exhibited similar neutron fluxes in irradiation channels, negative feedback of temperature and void coefficients, but the LEU is more radiotoxic after fission product decay due to higher actinides presence at the end of its core lifetime.
Download or read book Masters Theses in the Pure and Applied Sciences written by Wade H. Shafer and published by Springer Science & Business Media. This book was released on 2013-11-21 with total page 307 pages. Available in PDF, EPUB and Kindle. Book excerpt: Masters Theses in the Pure and Applied Sciences was first conceived, published, and dis· seminated by the Center for Information and Numerical Data Analysis and Synthesis (CINDAS) *at Purdue University in 1957, starting its coverage of theses with the academic year 1955. Beginning with Volume 13, the printing and dissemination phases of the ac· tivity 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 concerned if the printing and distribution of the volume were handled by an international 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 Corporation 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 20 (thesis year 1975) a total of 10,374 theses titles from 28 Canadian and 239 United States universities. We are sure that this broader base for theses titles reported will greatly enhance the value of this important annual reference work. The organization of Volume 20 is identical to that of past years. It consists of theses titles arranged by discipline and by university within each discipline.
Download or read book Physics of Plutonium Recycling written by OECD Nuclear Energy Agency. Working Party on Physics of Plutonium Recycling and published by . This book was released on 2003 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics of Plutonium Recycling written by OECD Nuclear Energy Agency. Working Party on Physics of Plutonium Recycling and published by . This book was released on 1995 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics of Plutonium Recycling Plutonium recycling in fast reactors written by NEA Nuclear Science Committee. Working Party on Physics of Plutonium Recycling and published by . This book was released on 1995 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics of Plutonium Recycling Fast plutonium burner reactors beginning of life written by OECD Nuclear Energy Agency. Working Party on Physics of Plutonium Recycling and published by . This book was released on 1995 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics of Plutonium Recycling Fast plutonium burner reactors beginning of life written by NEA Nuclear Science Committee. Working Party on Physics of Plutonium Recycling and published by Nuclear and Dev. This book was released on 1995 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt: On cover & title page: OECD Documents
Download or read book Issues and Perspectives written by and published by . This book was released on 1995 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Plutonium Utilization Program Technical Activities Quarterly Report written by and published by . This book was released on 1969 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Self sustaining Plutonium Recycle in Sodium Graphite Reactors written by T. J. Connolly and published by . This book was released on 1959 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 700 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Approach to Critical and Calibration Experiments in the Plutonium Recycle Critical Facility written by R. A. Bennett and published by . This book was released on 1964 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics of Plutonium Recycling Multiple pu recycling in advanced PWRs written by NEA Nuclear Science Committee. Working Party on Physics of Plutonium Recycling and published by . This book was released on 1995 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt:
