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A Physical Description Of Fission Product Behavior Fuels For Advanced Power Reactors
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Book Synopsis A Physical Description of Fission Product Behavior Fuels for Advanced Power Reactors by :
Download or read book A Physical Description of Fission Product Behavior Fuels for Advanced Power Reactors written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Global Nuclear Energy Partnership (GNEP) is considering a list of reactors and nuclear fuels as part of its chartered initiative. Because many of the candidate materials have not been explored experimentally under the conditions of interest, and in order to economize on program costs, analytical support in the form of combined first principle and mechanistic modeling is highly desirable. The present work is a compilation of mechanistic models developed in order to describe the fission product behavior of irradiated nuclear fuel. The mechanistic nature of the model development allows for the possibility of describing a range of nuclear fuels under varying operating conditions. Key sources include the FASTGRASS code with an application to UO2 power reactor fuel and the Dispersion Analysis Research Tool (DART) with an application to uranium-silicide and uranium-molybdenum research reactor fuel. Described behavior mechanisms are divided into subdivisions treating fundamental materials processes under normal operation as well as the effect of transient heating conditions on these processes. Model topics discussed include intra- and intergranular gas-atom and bubble diffusion, bubble nucleation and growth, gas-atom re-solution, fuel swelling and?scion gas release. In addition, the effect of an evolving microstructure on these processes (e.g., irradiation-induced recrystallization) is considered. The uranium-alloy fuel, U-xPu-Zr, is investigated and behavior mechanisms are proposed for swelling in the [alpha]-, intermediate- and [gamma]-uranium zones of this fuel. The work reviews the FASTGRASS kinetic/mechanistic description of volatile?scion products and, separately, the basis for the DART calculation of bubble behavior in amorphous fuels. Development areas and applications for physical nuclear fuel models are identified.
Book Synopsis Experiments on the Release of Fission Products from Molten Reactor Fuels by : G. E. Creek
Download or read book Experiments on the Release of Fission Products from Molten Reactor Fuels written by G. E. Creek and published by . This book was released on 1959 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Inventory and Decay Heat Associated with FTR Fuel by : W. L. Bunch
Download or read book Fission Product Inventory and Decay Heat Associated with FTR Fuel written by W. L. Bunch and published by . This book was released on 1969 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt: The fission product inventory and the decay heat associated with driver fuel irradiated to goal exposure (45,000 MWd per metric ton) in the Fast Test Reactor is presented, based on calculations using the computer code RIBD with a nuclear data library prepared for the FTR environment. Curie inventories as a function of decay time are given for each of about 350 isotopes or isomeric states generated by the fast-neutron induced fission of either 239Pu or 238U, by down-chain decay, or by subsequent neutron capture. Beta, gamma, and total decay power are given in percent of operating power for decay times from 1 sec to about 10 years. Uncertainty in the decay heat calculations, based on propagation of the uncertainties associated with input nuclear data, is estimated. The uncertainty is calculated to be less than +̲ 10% for the first 10 days, and less than +̲ 20% over a 10-yr decay period.
Book Synopsis Fission Product Release and Fuel Behavior of Irradiated Light Water Reactor Fuel Under Severe Accident Conditions by :
Download or read book Fission Product Release and Fuel Behavior of Irradiated Light Water Reactor Fuel Under Severe Accident Conditions written by and published by . This book was released on 1991 with total page 273 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Investigation of Fission Product Behavior and Decay Heating in Nuclear Reactors by : Talmadge Ray England
Download or read book An Investigation of Fission Product Behavior and Decay Heating in Nuclear Reactors written by Talmadge Ray England and published by . This book was released on 1970 with total page 696 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission product release and fuel behavior of irradited light water reactor fuel under severe accident conditions : the ACRR ST-1 experiment by : M. D. Allen
Download or read book Fission product release and fuel behavior of irradited light water reactor fuel under severe accident conditions : the ACRR ST-1 experiment written by M. D. Allen and published by . This book was released on 1991 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel by :
Download or read book Feasibility and Safety Assessment for Advanced Reactor Concepts Using Vented Fuel written by and published by . This book was released on 2015 with total page 352 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent interest in fast reactor technology has led to renewed analysis of past reactor concepts such as Gas Fast Reactors and Sodium Fast Reactors. In an effort to make these reactors more economic, the fuel is required to stay in the reactor for extended periods of time; the longer the fuel stays within the core, the more fertile material is converted into usable fissile material. However, as burnup of the fuel-rod increases, so does the internal pressure buildup due to gaseous fission products. In order to reach the 30 year lifetime requirements of some reactor designs, the fuel pins must have a vented-type design to allow the buildup of fission products to escape. The present work aims to progress the understanding of the feasibility and safety issues related to gas reactors that incorporate vented fuel. The work was separated into three different work-scopes: 1. Quantitatively determine fission gas release from uranium carbide in a representative helium cooled fast reactor; 2. Model the fission gas behavior, transport, and collection in a Fission Product Vent System; and, 3. Perform a safety analysis of the Fission Product Vent System. Each task relied on results from the previous task, culminating in a limited scope Probabilistic Risk Assessment (PRA) of the Fission Product Vent System. Within each task, many key parameters lack the fidelity needed for comprehensive or accurate analysis. In the process of completing each task, the data or methods that were lacking were identified and compiled in a Gap Analysis included at the end of the report.
Book Synopsis Fission Product Behavior During the PBF Severe Fuel Damage Test 1-1 by : Jack K. Hartwell
Download or read book Fission Product Behavior During the PBF Severe Fuel Damage Test 1-1 written by Jack K. Hartwell and published by . This book was released on 1987 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations by : Kilian Kern
Download or read book Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations written by Kilian Kern and published by . This book was released on 2020-10-09 with total page 250 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission product yield data play an important role in simulations of nuclear fission reactors, aimed at fuel cycle and safety analyses. The respective evaluated data libraries still have shortcomings regarding the treatment of energy dependencies and uncertainty information. This work has been aimed at the development of a fission model for future fission product yield evaluations as well as its validation on the levels of cross-sections, fission product yields and time dependent decay radiation. This work was published by Saint Philip Street Press pursuant to a Creative Commons license permitting commercial use. All rights not granted by the work's license are retained by the author or authors.
Book Synopsis Science of Advanced LMFBR Fuels by : Hj Matzke
Download or read book Science of Advanced LMFBR Fuels written by Hj Matzke and published by North Holland. This book was released on 1986 with total page 762 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Release & Fuel Behavior of Irradiated Light Water Reactor Fuel Under Servere Accident Conditions ... Etc by :
Download or read book Fission Product Release & Fuel Behavior of Irradiated Light Water Reactor Fuel Under Servere Accident Conditions ... Etc written by and published by . This book was released on 1991 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Irradiation Experiment by :
Download or read book Comparison of Fission Product Release Predictions Using PARFUME with Results from the AGR-1 Irradiation Experiment written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents comparisons between post-irradiation examination measurements and model predictions of silver (Ag), cesium (Cs), and strontium (Sr) release from selected tristructural isotropic (TRISO) fuel particles and compacts during the first irradiation test of the Advanced Gas Reactor program that occurred from December 2006 to November 2009 in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). The modeling was performed using the particle fuel model computer code PARFUME (PARticle FUel ModEl) developed at INL. PARFUME is an advanced gas-cooled reactor fuel performance modeling and analysis code (Miller 2009). It has been developed as an integrated mechanistic code that evaluates the thermal, mechanical, and physico-chemical behavior of fuel particles during irradiation to determine the failure probability of a population of fuel particles given the particle-to-particle statistical variations in physical dimensions and material properties that arise from the fuel fabrication process, accounting for all viable mechanisms that can lead to particle failure. The code also determines the diffusion of fission products from the fuel through the particle coating layers, and through the fuel matrix to the coolant boundary. The subsequent release of fission products is calculated at the compact level (release of fission products from the compact) but it can be assessed at the particle level by adjusting the diffusivity in the fuel matrix to very high values. Furthermore, the diffusivity of each layer can be individually set to a high value (typically 10-6 m2/s) to simulate a failed layer with no capability of fission product retention. In this study, the comparison to PIE focused on fission product release and because of the lack of failure in the irradiation, the probability of particle failure was not calculated. During the AGR-1 irradiation campaign, the fuel kernel produced and released fission products, which migrated through the successive layers of the TRISO-coated particle and potentially through the compact matrix. The release of these fission products was measured in PIE and modeled with PARFUME.
Book Synopsis Fission Product Monitoring of TRISO Coated Fuel For The Advanced Gas Reactor -1 Experiment by :
Download or read book Fission Product Monitoring of TRISO Coated Fuel For The Advanced Gas Reactor -1 Experiment written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US Department of Energy has embarked on a series of tests of TRISO-coated particle reactor fuel intended for use in the Very High Temperature Reactor (VHTR) as part of the Advanced Gas Reactor (AGR) program. The AGR-1 TRISO fuel experiment, currently underway, is the first in a series of eight fuel tests planned for irradiation in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The AGR-1 experiment reached a peak compact averaged burn up of 9% FIMA with no known TRISO fuel particle failures in March 2008. The burnup goal for the majority of the fuel compacts is to have a compact averaged burnup greater than 18% FIMA and a minimum compact averaged burnup of 14% FIMA. At the INL the TRISO fuel in the AGR-1 experiment is closely monitored while it is being irradiated in the ATR. The effluent monitoring system used for the AGR-1 fuel is the Fission Product Monitoring System (FPMS). The FPMS is a valuable tool that provides near real-time data indicative of the AGR-1 test fuel performance and incorporates both high-purity germanium (HPGe) gamma-ray spectrometers and sodium iodide [NaI(Tl)] scintillation detector-based gross radiation monitors. To quantify the fuel performance, release-to-birth ratios (R/B's) of radioactive fission gases are computed. The gamma-ray spectra acquired by the AGR-1 FPMS are analyzed and used to determine the released activities of specific fission gases, while a dedicated detector provides near-real time count rate information. Isotopic build up and depletion calculations provide the associated isotopic birth rates. This paper highlights the features of the FPMS, encompassing the equipment, methods and measures that enable the calculation of the release-to-birth ratios. Some preliminary results from the AGR-1 experiment are also presented.
Book Synopsis The Effect of Fission Product Accumulation on the Physical Condition of Fast Reactor Fuel Elements by : United Kingdom Atomic Energy Authority
Download or read book The Effect of Fission Product Accumulation on the Physical Condition of Fast Reactor Fuel Elements written by United Kingdom Atomic Energy Authority and published by . This book was released on 1953 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Analysis of the Behavior of Fission Product Gas in Solid Fast Reactor Oxide Fuel Under Transient Heating Conditions by : José Walderley Coêlho Dias
Download or read book Analysis of the Behavior of Fission Product Gas in Solid Fast Reactor Oxide Fuel Under Transient Heating Conditions written by José Walderley Coêlho Dias and published by . This book was released on 1973 with total page 472 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Safety in Light Water Reactors by : Bal Raj Sehgal
Download or read book Nuclear Safety in Light Water Reactors written by Bal Raj Sehgal and published by Academic Press. This book was released on 2012-01-05 with total page 732 pages. Available in PDF, EPUB and Kindle. Book excerpt: La 4e de couverture indique : Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information.
Book Synopsis NUREG/CR. by : U.S. Nuclear Regulatory Commission
Download or read book NUREG/CR. written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1977 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
