Download or read book Fuel Burnup Studies for a Pressurized water Reactor written by James P. Cunningham and published by . This book was released on 1958 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effects of Changing Economic Conditions on Fuel Cycle Costs in Pressurized Water Reactors written by Manson Benedict and published by . This book was released on 1963 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: A study made by MIT for ECNG of the effect of changing economic conditions on fuel cycle costs in nuclear power systems is described. Fuel cycle costs are computed for eight different cost bases, which may be used to represent the effect of most of the combinations of economic condi tions likely to occur during the life of the reactor selected for study. This is an advanced pressurized-water reactor with free-standing stainless steel of Zircaloy fuel cladding, designed for a net electric output of 461 Mw. (Author).
Download or read book The Shippingport Pressurized Water Reactor written by and published by . This book was released on 1958 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Advanced Pressurized Water Reactor Study written by U.S. Atomic Energy Commission. Division of Reactor Development and published by . This book was released on 1959 with total page 510 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Design Strategies for Optimizing High Burnup Fuel in Pressurized Water Reactors written by Zhiwen Xu and published by . This book was released on 2003 with total page 305 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work is focused on the strategy for utilizing high-burnup fuel in pressurized water reactors (PWR) with special emphasis on the full array of neutronic considerations. The historical increase in batch-averaged discharge fuel burnup, from ~30 MWd/kg in the 1970s to ~50 MWd/kg today, was achieved mainly by increasing the reload fuel enrichment to allow longer fuel cycles: from an average of 12 months to about 18 months. This also reduced operating costs by improving the plant capacity factor. Recently, because of limited spent fuel storage capacity, increased core power output and the search for increased proliferation resistance, achieving burnup in the 70 to 100 MWd/kg range has attracted considerable attention. However the implications of this initiative have not been fully explored; hence this work defines the practical issues for high-burnup PWR fuels based on neutronic, thermal hydraulic and economic considerations as well as spent fuel characteristics. In order to evaluate the various high burnup fuel design options, an improved MCNP-ORIGEN depletion program called MCODE was developed. A standard burnup predictor-corrector algorithm is implemented, which distinguishes MCODE from other MCNP-ORIGEN linkage codes. Using MCODE, the effect of lattice design (moderation effect) on core design and spent fuel characteristics is explored. Characterized by the hydrogen-to-heavy-metal ratio (H/HM), the neutron spectrum effect in UO2/H2O lattices is investigated for a wide range of moderation, from fast spectra to over-thermalized spectra. It is shown that either wetter or very dry lattices are preferable in terms of achievable burnup potential to those having an epithermal spectrum. Wet lattices are the preferred high burnup approach due to improved proliferation resistance. The constraint of negative moderator temperature coefficient (MTC) requires that H/HM values (now at 3.4) remain below ~6.0 for PWR lattices. Alternative fuel choices, including the conventional solid pellets, central-voided annular pellets, Internally- & eXternally-cooled Annular Fuel (IXAF), and different fuel forms are analyzed to achieve a wetter lattice. Although a wetter lattice has higher burnup potential than the reference PWR lattice, the requirement of a fixed target cycle energy production necessitates higher initial fuel enrichments to compensate for the loss of fuel mass in a wetter lattice. Practical issues and constraints for the high burnup fuel include neutronic reactivity control, heat transfer margin, and fission gas release. Overall the IXAF design appears to be the most promising approach to realization of high burnup fuel. High-burnup spent fuel characteristics are compared to the reference spent fuel of 33 MWd/kg, representative of most of the spent fuel inventory. Although an increase of decay power and radioactivity per unit mass of initial heavy metal is immediately observed, the heat load (integration of decay power over time) per unit electricity generation decreases as the fuel discharge burnup increases. The magnitude of changes depends on the time after discharge. For the same electricity production, not only the mass and volume of the spent fuel are reduced, but also, to a lesser extent, the total heat load of the spent fuel. Since the heat load in the first several hundred years roughly determines the capital cost of the repository, a high burnup strategy coupled with adequate cooling time, may provide a cost-reduction approach to the repository. High burnup is beneficial to enhancing the proliferation resistance. The plutonium vector in the high-burnup spent fuel is degraded, hence less attractive for weapons. For example, the ratio of Pu-238 to Pu-239 increases with burnup to the 2.5 power. However, the economic benefits are uncertain. Under the current economic conditions, the PWR fuel burnup appears to have a shallow optimum discharge burnup between 50 and 80 MWd/kg. The actual minimum is influenced by the financing costs as well as the cost of refueling shutdowns. Since the fuel cycle back-end benefits will accrue to the federal government, the current economic framework, such as the waste fee based on the electricity produced rather than volume or actinide content, does not create an incentive for utilities to increase burnup. Different schemes exist for fuel management of high burnup PWR cores. For the conventional core design, a generalized enrichment-burnup correlation (applicable between 3 w/o and 20 w/o) was produced based on CASMO/SIMULATE PWR core calculations. Among retrofit cores, increasing the number of fuel batches is preferred over increasing the cycle length due to nuclear fuel cycle economic imperatives. For future core designs, a higher power-density core is a very attractive option to cut down the busbar cost. The IXAF concept possesses key design characteristics that provide the necessary thermal margins at high core power densities. In this regard, the IXAF fuel deserves further investigation to fully exploit its high burnup capability.
Download or read book Review and Prioritization of Technical Issues Related to Burnup Credit for Bwr Fuel written by U.s. Nuclear Reglatory Commission and published by CreateSpace. This book was released on 2014-05-20 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report has been prepared to support technical discussion of and planning for future research supporting implementation of burnup credit for boiling-water reactor (BWR) spent fuel storage in spent fuel pools and storage and transport cask applications. The review and discussion in this report are based on knowledge and experience gained from work performed in the United States and other countries, including experience with burnup credit for pressurized-water reactor (PWR) spent fuel. Relevant physics and analysis phenomena are identified, and an assessment of their importance to burnup credit implementation is given. Results from sensitivity studies of some of the key phenomena are presented.
Download or read book Fully Automated 3 D Parallel Simulation and Optimization of a Full Scale Pressurized Water Reactor Fuel Assembly with Burnup Corrected Cross Sections written by Thomas Joseph Plower and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: ABSTRACT: Computational nuclear fuel burnup analysis is an essential field within the Nuclear Engineering discipline, since it plays important functions in core reactivity management, criticality safety, Special Nuclear Materials management, and fuel assembly reload design of commercial power and research reactors. Three dimensional (3-D) deterministic transport methods provides unique advantages in the fuel burnup analysis field and the intention of this thesis is to demonstrate the author's contributions to the development of a novel 3-D deterministic fuel burnup package called the PENTRAN /PENBURN (Parallel Environment Neutral particle Transport/Parallel Environment Burnup) suite. Specifically, cross section generation procedures will be presented including discussions on development of a coupled cross section interpolator code called INTERP-XS. Additionally, detailed fuel burnup analysis of a 17x17 PWR assembly will be presented. Finally, the development of an automated sequence driver called BURNDRIVER will be shown. Major conclusions include: excellent agreement between INTERP-XS generated cross sections and those generated by SCALE, demonstration of 3-D burnup effects captured by PENTRAN/PENBURN through PWR assembly analysis, and successful creation of a user-friendly burnup sequence driver.
Download or read book Fuel Burnup Studies for a 255 Mwe Advanced Sodium Graphite Reactor written by A. L. Aronson and published by . This book was released on 1960 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reliability of Advanced High Power Extended Burnup Pressurized Heavy Water Reactor Fuels written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2019-05-22 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication presents a comprehensive summary of the technical work carried out under an IAEA coordinated research project (CRP) and provides an overview of Member States' approaches to mitigate challenges that are encountered in achieving reliability, sustainability and safety with advanced pressurized heavy water reactor (PHWR) fuels. These challenges, which were discussed and analyzed by the CRP participants, include fuel performance degradation, insufficient availability of operating experience at high burnup and margin erosion by ageing.
Download or read book Experience in Computing Research Reactor Fuel Burnup Contrasted with Recovery Results written by and published by . This book was released on 1967 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reliability of Advanced High Power Extended Burnup Pressurized Heavy Water Reactor Fuels written by IAEA. and published by . This book was released on 2019 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Safety Research Programs written by S. K. Edler and published by . This book was released on 1983 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Detailed Analysis of Phase Space Effects in Fuel Burnup depletion for PWR Assembly Full Core Models Using Large scale Parallel Computation written by Kevin Manalo and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear nonproliferation research and forensics have a need for improved software solutions, particularly in the estimates of the transmutation of nuclear fuel during burnup and depletion. At the same time, parallel computers have become effectively sized to enable full core simulations using highly-detailed 3d mesh models. In this work, the capability for modeling 3d reactor models is researched with PENBURN, a burnup/depletion code that couples to the PENTRAN Parallel Sn Transport Solver and also to the Monte Carlo solver MCNP5 using the multigroup option. This research is computationally focused, but will also compare a subset of results of experimental Pressurized Water Reactor (PWR) burnup spectroscopy data available with a designated BR3 PWR burnup benchmark. Also, this research will analyze large-scale Cartesian mesh models that can be feasibly modeled for 3d burnup, as well as investigate the improvement of finite differencing schemes used in parallel discrete ordinates transport with PENTRAN, in order to optimize runtimes for full core transport simulation, and provide comparative results with Monte Carlo simulations. Also, the research will consider improvements to software that will be parallelized, further improving large model simulation using hybrid OpenMP-MPI. The core simulations that form the basis of this research, utilizing discrete ordinates methods and Monte Carlo methods to drive time and space dependent isotopic reactor production using the PENBURN code, will provide more accurate detail of fuel compositions that can benefit nuclear safety, fuel management, non-proliferation, and safeguards applications.
Download or read book Fuel Cycle Program a Boiling Water Reactor Research and Development Program written by and published by . This book was released on 1960-08 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Extended Burnup Fuel Cycle Optimization for Pressurized Water Reactors written by Alfred Lee-Bin Ho and published by . This book was released on 1981 with total page 176 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Optimization Study for Large Pressurized Water Reactor Cores written by L. E. Strawbridge and published by . This book was released on 1964 with total page 246 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Optimization of In core Nuclear Fuel Management in a Pressurized Water Reactor written by Richard Bartholomew Stout and published by . This book was released on 1972 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fuel loading patterns which have a minimum power peak are economically desirable to allow power reactors to operate at the highest possible power density and to minimize the possibility of fuel failure. A computer code called SHUFLE was developed for pressurized water reactors which shuffles the fuel in search of the lowest possible power peaking factor. An iterative approach is used in this search routine. A radial power distribution is calculated from which the program logic Selects a movement of fuel elements in an attempt to lower the radial power peak. Another power calculation is made and the process repeated until a predetermined convergence is reached. The logic by which the code decides the fuel movement is presented, along with the criteria for accepting or rejecting the move after a power calculation of the new loading pattern is made. A 1.5 group course mesh diffusion theory method was used to obtain the power distribution for each SHUFLE iteration. Convergence to a final loading pattern varies from about 10 to 40 shuffling iterations depending on the initial loading presented to the code. Since the typical computer running time for a one-quarter core power distribution with this 1.5 group method is only one to a few seconds, depending on the loading, convergence to a good loading pattern takes on the order of one minute on a Univac 1108. The low computer cost plus ease of operation should make this code of considerable use in determining loading patterns with minimum power peaking for any given set of fuel elements. The program also has burnup capability which can be used to check power peaking throughout core life. A parametric analysis study of fuel cycle costs for a PWR is also presented. Cost parameters analyzed were variation in the cost of yellow cake, enrichment, money, fabrication, and reprocessing plus changes in burnup, load factors, power densities, and the effect of forced early discharge. Figures are presented to indicate total fuel costs as a function of burnup for these cost parameters. Linear relationships for minimum cost and optimum burnup are presented for each parameter.
