Download or read book Assessment of the Use of Extended Burnup Fuel in Light Water Power Reactors written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Water Reactor Fuel Extended Burnup Study written by International Atomic Energy Agency and published by . This book was released on 1992 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Extended burnup LWR Fuel written by W. J. Bailey and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book DOE Program to Improve Uranium Utilization in Light Water Reactors Environmental Assessment EA written by and published by . This book was released on 1980 with total page 110 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Spent Light Water Power Reactor Fuel Handling and Storage written by and published by . This book was released on 1979 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Energy Research Initiative written by and published by . This book was released on 2000 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Energy Research Initiative: Development of a Stabilized Light Water Reactor Fuel Matrix for Extended Burnup.
Download or read book Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit Perspectives and Challenges written by International Atomic Energy Agency and published by . This book was released on 2020-10-12 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: The limitation of 235U enrichment is a current concern among IAEA Member States. In response, work has been undertaken to provide a platform to facilitate a comprehensive review of the current status, prospects and challenges associated with the use of fuels having enrichments higher than 5 % 235U in light water reactors. This publication is the outcome of two technical meetings and compiles the results and conclusions in terms of benefits to be obtained from the use of high assay low enriched uranium (HALEU) fuel, with due consideration of safety issues that arise from its use. It details technological options and corresponding issues regarding fuel and core design, safety analysis and assessments relevant to manufacturing, handling, transportation, storage, irradiation, and performance in normal and accident conditions.
Download or read book The Burnup Dependence of Light Water Reactor Spent Fuel Oxidation written by Brady Dean Hanson and published by . This book was released on 1998 with total page 474 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Preliminary safety and environmental information document written by Argonne National Laboratory and published by . This book was released on 1980 with total page 584 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Impact of High Burnup Uranium Oxide and Mixed Uranium plutonium Oxide Water Reactor Fuel on Spent Fuel Management written by International Atomic Energy Agency and published by . This book was released on 2011 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication examines the many aspects of the increased use of high burnup uranium oxide (UOX) and mixed oxide (MOX) fuel and its potential impact on spent fuel management as well as on the whole nuclear industry. It discusses reactor types, with emphasis on light water reactor (LWR) and heavy water reactor (HWR) technology, considers the current state of UOX and MOX worldwide, provides information on the various fuel and cladding types and spent fuel management component,s and elaborates on the characteristics of spent fuel related to higher burnup UOX and MOX fuels, followed by a detailed analysis. The publication also identifies areas for future research and development.
Download or read book Technical Report on Densification of Light Water Reactor Fuels written by U.S. Atomic Energy Commission and published by . This book was released on 1972 with total page 180 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Extended Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: [Full Text] Oak Ridge National Laboratory and the United States Nuclear Regulatory Commission have initiated a multiyear project to investigate the application of burnup credit (BUC) for boiling-water reactor (BWR) fuel in storage and transportation casks. This project includes two phases. The first phase investigates the applicability of peak reactivity methods currently used for spent fuel pools to spent fuel storage and transportation casks and the validation of reactivity (keff) calculations and depleted fuel compositions. The second phase focuses on extending BUC beyond peak reactivity. This paper documents work performed to date, investigating some aspects of extended BUC, and it also describes the plan to complete the evaluations. The technical basis for application of peak reactivity methods to BWR fuel in storage and transportation systems is presented in a companion paper. Two reactor operating parameters are being evaluated to establish an adequate basis for extended BWR BUC, including investigation of the axial void profile effect and the effect of control blade utilization during operation. A detailed analysis of core simulator data for one cycle of an operating BWR plant was performed to determine the range of void profiles and the variability of the profile experienced during irradiation. While a single cycle does not provide complete data, the data obtained are sufficient to use to determine the primary effects and identify conservative modeling approaches. Using data resulting from a single cycle, the axial void profile is studied by first determining the temporal fidelity necessary in depletion modeling, and then using multiple void profiles to examine the effect of the void profile on cask reactivity. The results of these studies are being used to develop recommendations for conservatively modeling the void profile effects for BWR depletion calculations. The second operational parameter studied is control blade exposure. Control blades are inserted in various locations and at varying degrees during BWR operation based on the reload design. The presence of control blades during depletion hardens the neutron spectrum locally due to both moderator displacement and introduction of a thermal neutron absorber. The reactivity impact of control blade presence is investigated herein, as well as the effect of multiple (continuous and intermittent) exposure periods. The coupled effects of control blade presence on power density, void profile, or burnup profile have not been considered to date but will be addressed in future work.
Download or read book Principles of Design Improvement for Light Water Reactors written by Long-sun Tong and published by Chem/Mats-Sci/E. This book was released on 1988 with total page 424 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Extension of Fuel Burnup in Light Water Reactors by Using a Strict In out Refueling Scheme written by Julian Yu-liang Yen and published by . This book was released on 1982 with total page 400 pages. Available in PDF, EPUB and Kindle. Book excerpt: To utilize energy resources as efficiently as possible has become a necessity today. The purpose of this study is to see how this can be done by extending burnup in a light water reactor. Specifically, an in-out refueling scheme might extract the maximum energy from nuclear fuel during its redidence in the reactor. In principle, a reactor loading with minimum neutron leakage and minimum parasitic absorption will best utilize the neutrons. For this, having more fissions near the center of the reactor will reduce leakage, and parasitic absorption by control elements could be reduced by having smaller reactivity changes between reloads. An in-out refueling scheme, i.e., loading the fresh fuel into the center of the reactor, moving the older fuel outward and removing the oldest fuel from the edge, could best utilize the reactivity of fresh fuel. This is because neutron importance is highest in the center. Placing control preferentially near the center then requires relatively less absorption in control elements to achieve a given degree of reactor control. The non-uniform flux distribution, with peaking at the center, will save neutrons because the fuel assemblies of the lowest neutron production capability are located at the edge of the reactor, and leakage from these fuels is neither very large nor very important. To simulate the in-out operation of the reactor in this study, two computer codes have been established. One is a one-dimensional code utilizing two group diffusion equations in an iteration scheme, and the other is a two-dimensional code using spatial flux synthesis. Studies have been made of the effects of the in-out refueling scheme on reactor cycle length, fuel burnup level, power peaking factor and other reactor characteristics. Results show that an in-out refueling scheme could have a fuel burnup benefit over the conventional (out-in) refueling scheme. The benefit can be up to 13 percent or more, depending on the frequency of refueling, the fuel design and the reactor size, compared with out-in refueling under the same circumstances. The in-out refueling scheme with short cycle length gets part of its benefit from frequent refueling. However, frequent refueling tends to expose the fuels at the center of the core to very high power peak ing. Peaking is a function of batch size (the smaller the batch size the higher the peak), and is closely related to the initial reactivity of the fuel, as well as to the method of fuel management. High power peaking can be alleviated by confining the reactivity-controlling absorber to the center of the reactor. Moreover, with this type of control the cycle length and discharge burnup become larger, for a given replacement batch size, than for a case in which control is applied over the whole core. Enrichment certainly could elongate the cycle length and so the discharge burnup, but the gain of burnup per enrichment increment decreases with enrichment level. Lattice design could also have some effects on the discharge burnup. More moderation of neutrons in a looser lattice increases the initial reactivity of the fuel, although it speeds up the rate of reactivity loss per flux-time. The low conversion of the fertile material in the fuel of a loose lattice does not apparently have as much influence on the discharge burnup as the initial reactivity does.
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 The Economics of the Nuclear Fuel Cycle written by OECD Nuclear Energy Agency and published by Nuclear Energy Agency, Organisation for Economic Co-operation and Development ; Washington, D.C. : OECD Publications and Information Centre. This book was released on 1994 with total page 186 pages. Available in PDF, EPUB and Kindle. Book excerpt:
