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Book Water Reactor Fuel Extended Burnup Study

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:

Book Extended burnup LWR Fuel

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:

Book Nuclear Energy Research Initiative

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.

Book Reliability of Advanced High Power Extended Burnup Pressurized Heavy Water Reactor Fuels

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.

Book Nuclear Energy Research Initiative

Download or read book Nuclear Energy Research Initiative written by and published by . This book was released on 2000 with total page 26 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.

Book Extension of Fuel Burnup in Light Water Reactors by Using a Strict In out Refueling Scheme

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.

Book Uranium Dioxide

Download or read book Uranium Dioxide written by J. Belle and published by . This book was released on 1961 with total page 744 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Economics of the Nuclear Fuel Cycle

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:

Book Extended Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems

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.

Book Improvements in Water Reactor Fuel Technology and Utilization

Download or read book Improvements in Water Reactor Fuel Technology and Utilization written by International Atomic Energy Agency and published by . This book was released on 1987 with total page 644 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Improved Utilization of Water Reactor Fuel with Special Emphasis on Extended Burnups and Plutonium Recycling

Download or read book Improved Utilization of Water Reactor Fuel with Special Emphasis on Extended Burnups and Plutonium Recycling written by International Working Group on Water Reactor Fuel Performance and Technology, International Atomic Energy Agency and published by . This book was released on 1984 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fuel Burnup Studies for a Pressurized water Reactor

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: