Download or read book Fission Gas Induced Fuel Swelling in Low and Medium Burnup Fuel During High Temperature Transients PWR written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The behavior of light water reactor fuel elements under postulated accident conditions is being studied by the EG and G Idaho, Inc., Thermal Fuels Behavior Program for the Nuclear Regulatory Commission. As a part of this program, unirradiated and previously irradiated, pressurized-water-reactor type fuel rods were tested under power-cooling-mismatch (PCM) conditions in the Power Burst Facility (PBF). During these integral in-reactor experiments, film boiling was produced on the fuel rods which created high fuel and cladding temperatures. Fuel rod diameters increased in the film boiling region to a greater extent for irradiated rods than for unirradiated rods. The purpose of the study was to investigate and assess the fuel swelling which caused the fuel rod diameter increases and to evaluate the ability of an analytical code, the Gas Release and Swelling Subroutine - Steady-State and Transient (GRASS-SST), to predict the results.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1982 with total page 998 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fuel swelling due to retained fission gas in molten fuel during high temperature transients written by K. Vinjamuri and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Energy Research Abstracts written by and published by . This book was released on 1982 with total page 1014 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book UO2 Fuel Behavior Under Power cooling mismatch Conditions written by Stephen L. Seiffert and published by . This book was released on 1981 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications written by Daniel Lee DeForest and published by . This book was released on 1991 with total page 466 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field

Download or read book Fission Gas Release from Fuel at High Burnup written by Ralph O. Meyer and published by . This book was released on 1978 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications written by Daniel Lee DeForest and published by . This book was released on 1991 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: In order to investigate whether fission gas swelling and release would be significant factors in a space based nuclear reactor operating under the Strategic Defense Initiative (SDI) program, the finite element program REDSTONE (Routine for Evaluating Dynamic Swelling in Transient Operational Nuclear Environments) was developed to model the 1-D, spherical geometry diffusion equations describing transient fission gas behavior in a single uranium nitride fuel grain. The equations characterized individual bubbles, rather than bubble groupings. This limited calculations to those scenarios where low temperatures, low burnups, or both were present. Instabilities in the bubble radii calculations forced the implementation of additional constraints limiting the bubble sizes to minimum and maximum (equilibrium) radii. The validity of REDSTONE calculations were checked against analytical solutions for internal consistency and against experimental studies for agreement with swelling and release results. These checks indicated that REDSTONE was satisfactorily accounting for the intragranular fission gas portion of swelling, but that other non-gaseous sources accounted for up to 1.5% additional swelling. A calculation was performed to determine the swelling and gas release associated with a hypothetical SDI scenario. The SDI scenario involved 10 years of low power operation at 10 kW followed by a 30 second rise to 1 MW which was maintained for approximately 15 minutes. The results indicated that the fuel pellet diametral increase would remain less than 1% and release would be negligible, far below that needed for design failure. This same scenario was run at higher temperatures to see if uncertainties in the operating parameters could cause significantly different results. It was apparent that further investigations into the swelling behavior near 1800°K were needed, as results indicated a significant shift to larger bubbles at this temperature. In an effort to understand the effect of property uncertainties on the solution, several of the properties were varied and the results compared. The largest effects were observed from changes in the irradiation enhanced diffusion coefficient and the resolution parameter. The resolution parameter uncertainty would have the largest potential effect on results, likely resulting in a reduction in the swelling and a corresponding increase in release.

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:

Download or read book Modeling the Performance of High Burnup Thoria and Urania PWR Fuel written by Yun Long and published by . This book was released on 2002 with total page 217 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) However, the gas diffusion coefficient in thoria was adjusted to a lower level to account for the smaller observed gas release fraction in the thoria-based fuel. To model accelerated fission gas release at high burnup properly, a new athermal fission gas release model was developed. Other modifications include the thoria fuel properties, fission gas production rate, and the corrosion model to treat advanced cladding materials. The modified version of FRAPCON-3 was calibrated using the measured fission gas release data from the Light Water Breeder Reactor (LWBR) program. Using the new model to calculate the gas release in typical PWR hot pins gives data that indicate that the ThO2-UO2 fuel will have considerably lower fission gas release beyond a burnup of 50 MWd/kgHM. Investigation of the fuel response to an RIA included: (1) reviewing industry simulation tests to understand the mechanisms involved, (2) modifying FRAP-T6 code to simulate the RIA tests and investigate the key contributors to fuel failure (thermal expansion, gaseous swelling, cladding burst stress), and (3) assessing thoria and urania performance during RIA event in typical LWR situations. ThO2-UO2 fuel has been found to have better performance than U02 fuel under RIA event conditions due to its lower thermal expansion and a flatter power distribution in the fuel pellet (less power and less fission gas in the rim region). Overall, thoria has been found to have better performance than urania in both normal and off-normal conditions. However, calculations using the modified FRAPCON-3 ...

Download or read book Fission Gas Release from High Burnup ThO sub 2 and ThO sub 2 UO sub 2 Fuels Irradiated at Low Temperature LWBR AWBA Development Program LWBR Below 2700 sup 0 F written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission gas release data are presented for five fuel rods irradiated at low fuel temperature (below 2700/sup 0/F) with burnups up to 90,000 MWD/MTM. Four of these rods contained ThO/sub 2/-UO/sub 2/ (33.6 weight percent UO/sub 2/) fuel pellets; the fifth rod contained ThO/sub 2/ pellets. These data supplement fission gas release information previously reported for 54 rods containing ThO/sub 2/-UO/sub 2/ and ThO/sub 2/ fuel, some of which experienced fuel temperaures up to 5000/sup 0/F and burnups to 56,000 MWD/MTM. These new data suggest that at burnups exceeding about 80,000 MWD/MTM a sharp increase in fission gas release occurs, possibly caused by microstructural changes in the fuel. This is similar to the behavior of UO/sub 2/ except that the increase occurs in UO/sub 2/ at lower burnup (approximately 40,000 MWD/MTM). The fission gas release calculational model previously reported has been modified to account for the observed increase in the low temperature component. The revised model provides a good best estimate of all the fission gas release data.

Download or read book Fission Gas Behaviour in Water Reactor Fuels written by and published by Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development. This book was released on 2002 with total page 572 pages. Available in PDF, EPUB and Kindle. Book excerpt: Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.

Download or read book A Fission Gas Release Correlation for Uranium Nitride Fuel Pins written by Michael B. Weinstein and published by . This book was released on 1973 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt: A model was developed to predict fission gas releases from UN fuel pins clad with various materials. The model was correlated with total release data obtained by different experimentors, over a range of fuel temperatures primarily between 1250 and 1660 K, and fuel burnups up to 4.6 percent. In the model, fission gas is transported by diffusion mechanisms to the grain boundaries where the volume grows and eventually interconnects with the outside surface of the fuel. The within grain diffusion coefficients are found from fission gas release rate data obtained using a sweep gas facility.

Download or read book Fission Gas Behavior in Mixed oxide Fuel During Transient Overpower and Simulated Loss of flow Tests written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A portion of the fission gases (Xe, Kr) generated during steady state irradiation of an FBR mixed-oxide fuel is retained within its microstructure, especially in the cooler regions of the fuel. Information on the behavior of these retained gases relative to their microstructural relocation and release during off-normal power and coolant flow conditions is important to the analysis and analytic modeling of fuel-pin transient and reactor core performance. This paper discusses the steady state and transient behavior of retained fission gas relative to the geometry, microstructure, temperature, and apparent release mechanisms within selected axial and radial regions of fuel pins irradiated at medium power (7 to 10 kW/ft) and burnup (30 to 60 MWd/kgm). The specific fuel pins are from the PNL-10 and PNL-2 subassemblies irradiated in EBR-II. The transient overpower tests involved integral fuel pin static capsule experiments performed in TREAT. Loss-of-coolant flow was simulated in an out-of-reactor thermal transient testing system using axial segments of irradiated fuel pins.

Download or read book Fission Gas Release from Oxide Fuels at High Burnups AWBA Development Program written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The steady state gas release, swelling and densification model previously developed for oxide fuels has been modified to accommodate the slow transients in temperature, temperature gradient, fission rate and pressure that are encountered in normal reactor operation. The gas release predictions made by the model were then compared to gas release data on LMFBR-EBRII fuels obtained by Dutt and Baker and reported by Meyer, Beyer, and Voglewede. Good agreement between the model and the data was found. A comparison between the model and three other sets of gas release data is also shown, again with good agreement.

Download or read book Assessment of Fission gas induced Transient Swelling in Metallic Fuel written by and published by . This book was released on 1985 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt: A model for fission-gas-induced transient swelling in metallic fuel is described. An observation that the strength of metallic fuel becomes very small at a temperature several hundred degrees below the solidus forms the basis for an assumption that, above this temperature, the fuel proceeds through a series of stress-free equilibrium states for a large range of heating rates. Gas bubble coalescence and growth and any effects from ingested sodium are ignored such that the model may tend to underestimate swelling in some circumstances. The fuel swelling model is used to predict the reactivity effect of fission-gas-induced axial expansion of metallic fuel during transient overpower excursions. Comparisons to oxide fuel behavior are made. Sensitivity of results to metallic fuel modeling assumptions are assessed in a parametric study.