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Book Fission Product Processes In Reactor Accidents

Download or read book Fission Product Processes In Reactor Accidents written by J. T. Rogers and published by CRC Press. This book was released on 2020-12-17 with total page 883 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.

Book Modeling of Fission Product Release from HTR high Temperature Reactor Fuel for Risk Analyses

Download or read book Modeling of Fission Product Release from HTR high Temperature Reactor Fuel for Risk Analyses written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US and FRG have developed methodologies to determine the performance of and fission product release from TRISO-coated fuel particles under postulated accident conditions. The paper presents a qualitative and quantitative comparison of US and FRG models. The models are those used by General Atomics (GA) and by the German Nuclear Research Center at Juelich (KFA/ISF). A benchmark calculation was performed for fuel temperatures predicted for the US Department of Energy sponsored Modular High Temperature Gas Cooled Reactor (MHTGR). Good agreement in the benchmark calculations supports the on-going efforts to verify and validate the independently developed codes of GA and KFA/ISF. This work was performed under the US/FRG Umbrella Agreement for Cooperation on Gas Cooled Reactor Development. 6 refs., 3 figs., 3 tabs.

Book Nuclear Safety in Light Water Reactors

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 Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1990 with total page 1044 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fission product release and fuel behavior of irradited light water reactor fuel under severe accident conditions the ACRR ST 1 experiment

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 Model for the Migration of the Fission Products Along the Coolant Channels of a High Temperature Gas Cooled Reactor Following a Hypothetical Accident of Complete Loss of Cooling

Download or read book Model for the Migration of the Fission Products Along the Coolant Channels of a High Temperature Gas Cooled Reactor Following a Hypothetical Accident of Complete Loss of Cooling written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Under the assumption that a nonmechanistic accident induces a condition such that it is not possible to cool the core of a high temperature gas cooled reactor, the temperature of the core will gradually rise due to decay heat. There are several barriers to the release of fission products to the environment: the fuel particle coatings, the graphite moderator, the prestressed concrete reactor vessel and the containment. A code, EVAP, has been written to calculate one stage in the release and migration of the fission products along the coolant channels. The calculations, using the code, are reported for 10 fission products, based on typical conditions which might occur in the course of the hypothetical accident. The sensitivity of the results to several important parameters is examined.

Book Fission Product Release from Fuel Under LWR Accident Conditions

Download or read book Fission Product Release from Fuel Under LWR Accident Conditions written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Three tests have provided additional data on fission product release under LWR accident conditions in a temperature range (1400 to 2000°C). In the release rate data are compared with curves from a recent NRC-sponsored review of available fission product release data. Although the iodine release in test HI-3 was inexplicably low, the other data points for Kr, I, and Cs fall reasonably close to the corresponding curve, thereby tending to verify the NRC review. The limited data for antimony and silver release fall below the curves. Results of spark source mass spectrometric analyses were in agreement with the gamma spectrometric results. Nonradioactive fission products such as Rb and Br appeared to behave like their chemical analogs Cs and I. Results suggest that Te, Ag, Sn, and Sb are released from the fuel in elemental form. Analysis of the cesium and iodine profiles in the thermal gradient tube indicates that iodine was deposited as CsT along with some other less volatile cesium compound. The cesium profiles and chemical reactivity indicate the presence of more than one cesium species.

Book Fission gas Release from Uranium Nitride at High Fission rate Density

Download or read book Fission gas Release from Uranium Nitride at High Fission rate Density 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 sweep gas facility has been used to measure the release rates of radioactive fission gases from small UN specimens irradiated to 8-percent burnup at high fission-rate densities. The measured release rates have been correlated with an equation whose terms correspond to direct recoil release, fission-enhanced diffusion, and atomic diffusion (a function of temperature). Release rates were found to increase linearly with burnups between 1.5 and 8 percent. Pore migration was observed after operation at 1550 K to over 6 percent burnup.

Book Fission Product Release from Highly Irradiated LWR Fuel

Download or read book Fission Product Release from Highly Irradiated LWR Fuel written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of experiments was conducted with highly irradiated light-water reactor fuel rod segments to investigate fission products released in steam in the temperature range 500 to 1200°C. (Two additional release tests were conducted in dry air.) The primary objectives were to quantify and characterize fission product release under conditions postulated for a spent-fuel transportation accident and for a successfully terminated loss-of-coolant accident (LOCA). In simulated, controlled LOCA-type tests, release at the time of rupture proved to be more significant than the diffusional release that followed. Comparison of the release data for the dry-air tests with the release data of similarly conducted tests in steam indicated significant increases in the releases of iodine, ruthenium, and cesium in air. Various parameters that affect fission product release are discussed, and experimental observations and analysis of the chemical behavior of releasable fission products in inert, steam, and dry-air atmospheres are examined.

Book Release of Fission Products During Controlled Loss of coolant Accidents and Hypothetical Core Meltdown Accidents PWR BWR

Download or read book Release of Fission Products During Controlled Loss of coolant Accidents and Hypothetical Core Meltdown Accidents PWR BWR written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A few years ago the Projekt Nukleare Sicherheit joined the United States Nuclear Regulatory Commission in the development of a research program which was designed to investigate fission product release from light water reactor fuel under conditions ranging from spent fuel shipping cask accidents to core meltdown accidents. Three laboratories have been involved in this cooperative effort. At Argonne National Laboratory (ANL), the research effort has focused on noble gas fission product release, whereas at Oak Ridge National Laboratory (ORNL) and at Kernforschungszentrum Karlsruhe (KfK), the studies have emphasized the release of species other than the noble gases. In addition, the ORNL program has been directed toward the development of fission product source terms applicable to analyses of spent fuel shipping cask accidents and controlled loss-of-coolant accidents, and the KfK program has been aimed at providing similar source terms which are characteristic of core meltdown accidents. The ORNL results are presented for fission product release from defected fuel rods into a steam atmosphere over the temperature range 500 to 1200°C, and the KfK results for release during core meltdown sequences.

Book Fission Product Release from High Gap inventory LWR Fuel Under LOCA Conditions

Download or read book Fission Product Release from High Gap inventory LWR Fuel Under LOCA Conditions written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission product release tests were performed with light water reactor (LWR) fuel rod segments containing large amounts of cesium and iodine in the pellet-to-cladding gap space in order to check the validity of the previously published Source Term Model for this type of fuel. The model describes the release of fission product cesium and iodine from LWR fuel rods for controlled loss-of-coolant accident (LOCA) transients in the temperature range 500 to 1200°C. The basis for the model was test data obtained with simulated fuel rods and commercial fuel irradiated to high burnup but containing relatively small amounts of cesium and iodine in the pellet-to-cladding gap space.