Download or read book Seismically Induced Core damage Accidents in the Clinch River Breeder Reactor Plant written by Martin A. Stutzke and published by . This book was released on 1984 with total page 202 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Studies of Unprotected Loss of flow Accidents for the Clinch River Breeder Reactor written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Studies of unprotected loss-of-flow accidents in the CRBR for various rates of flow coastdown and with various options in the SAS 3A code did not lead to conditions for a violent disassembly. Maximum fuel temperatures using the SLUMPY module for disassembly were in the range 4000--4500/sup 0/C. An approximate treatment of the LOF-driven TOP accident, not properly modeled by SAS 3A, indicates the possibility of some increase in accident severity. The effect of fission gas in dispersing fuel was not taken into account in these calculations. Parameter variations included the presence or absence of axial fuel expansion and of clad motion and use of the moving coolant film model versus the static film model. Study of severe pipe rupture accidents with scram indicated that pin power density and fuel-clad conductance were important parameters in determining what coolant flow rate was needed to prevent boiling after the rupture. It appears that for the CRBR when engineering hot channel factors are considered, this fraction would have to exceed 25 percent.

Download or read book Masters Theses in the Pure and Applied Sciences written by Wade H. Shafer and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 407 pages. Available in PDF, EPUB and Kindle. Book excerpt: Masters Theses in the Pure and Applied Sciences was first conceived, published, and disseminated by the Center for Information and Numerical Data Analysis and Synthesis (CINDAS) * at Purdue University in 1 957, starting its coverage of theses with the academic year 1955. Beginning with Volume 13, the printing and dissemination phases of the activity were transferred to University Microfilms/Xerox of Ann Arbor, Michigan, with the thought that such an arrangement would be more beneficial to the academic and general scientific and technical community. After five years of this joint undertaking we had concluded that it was in the interest of all con cerned if the printing and distribution of the volumes were handled by an interna tional publishing house to assure improved service and broader dissemination. Hence, starting with Volume 18, Masters Theses in the Pure and Applied Sciences has been disseminated on a worldwide basis by Plenum Publishing Cor poration of New York, and in the same year the coverage was broadened to include Canadian universities. All back issues can also be ordered from Plenum. We have reported in Volume 29 (thesis year 1984) a total of 12,637 theses titles from 23 Canadian and 202 United States universities. We are sure that this broader base for these titles reported will greatly enhance the value of this important annual reference work. While Volume 29 reports theses submitted in 1984, on occasion, certain univer sities do report theses submitted in previous years but not reported at the time.

Download or read book Modeling and Analysis of the Unprotected Loss of flow Accident in the Clinch River Breeder Reactor written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The influence of fission-gas-driven fuel compaction on the energetics resulting from a loss-of-flow accident was estimated with the aid of the SAS3D accident analysis code. The analysis was carried out as part of the Clinch River Breeder Reactor licensing process. The TREAT tests L6, L7, and R8 were analyzed to assist in the modeling of fuel motion and the effects of plenum fission-gas release on coolant and clad dynamics. Special, conservative modeling was introduced to evaluate the effect of fission-gas pressure on the motion of the upper fuel pin segment following disruption. For the nominal sodium-void worth, fission-gas-driven fuel compaction did not adversely affect the outcome of the transient. When uncertainties in the sodium-void worth were considered, however, it was found that if fuel compaction occurs, loss-of-flow driven transient overpower phenomenology could not be precluded.

Download or read book Clinch River Breeder Reactor Plant written by and published by . This book was released on 1977 with total page 472 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Primary Pipe Rupture Accident Analysis for the Clinch River Breeder Reactor written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In this report, the thermal transient response of the CRBR to a severe primary coolant flow perturbation, initiated by a rupture of the primary heat transport system piping, is analyzed. This hypothetical accident is studied under the further assumption that the plant protection system does function according to current design descriptions for the CRBR. Although a brief discussion of an unprotected (no scram) pipe rupture accident is presented, the major emphasis of the present report is on the protected accident.

Download or read book Estimated Recurrence Frequencies for Initiating Accident Categories Associated with the Clinch River Breeder Reactor Plant Design written by E. R. Copus and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Hypothetical Core Disassembly Accident Analysis for the Gas cooled Fast Reactor and Liquid Metal Fast Breeder Reactor written by David C. Losey and published by . This book was released on 1979 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Estimated Recurrence Frequencies for Initiating Accident Categories Associated with the Clinch River Breeder Reactor Plant Design written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Estimated recurrence frequencies for each of twenty-five generic LMFBR initiating accident categories were quantified using the Clinch River Breeder Reactor Plant (CRBRP) design. These estimates were obtained using simplified systems fault trees and functional event tree models from the Accident Delineation Study Phase I Final Report coupled with order-of-magnitude estimates for the initiator-dependent failure probabilities of the individual CRBRP engineered safety systems. Twelve distinct protected accident categories where SCRAM is assumed to be successful are estimated to occur at a combined rate of 10/sup -3/ times per year while thirteen unprotected accident categories in which SCRAM fails are estimated to occur at a combined rate on the order of 10/sup -5/ times per year. These estimates are thought to be representative despite the fact that human performance factors, maintenance and repair, as well as input common cause uncertainties, were not treated explicitly. The overall results indicate that for the CRBRP design no single accident category appears to be dominant, nor can any be totally eliminated from further investigation in the areas of accident phenomenology for in-core events and post-accident phenomenology for containment.

Download or read book Impact of Plenum fission gas driven Fuel Compaction on the Unprotected Loss of flow Accident in the Clinch River Breeder Reactor written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: As a part of the licensing process just prior to the termination of the Clinch River Breeder Reactor Project (CRBRP), it was necessary to evaluate the potential for autocatalysis in an unprotected loss-of-flow accident due to the compaction of fuel by gas stored in the fuel-pin fission gas plena. The SAS3D accident analysis code was used for the evaluation. There are several aspects to the present analysis. First, it was necessary to modify the gas release model in SAS3D to provide a better treatment of gas release after boiling initiation: gas entering the channel was converted to an equivalent source of sodium vapor and a significant reduction was made in the vapor condensation coefficient. Second, single-phase friction coupling between vapor and molten clad was introduced to produce more realistic clad motion prior to the onset of fuel motion. A third aspect of the analysis was the use of experimentally verified input assumptions for the SAS3D/SLUMPY fuel motion model. A fourth aspect was the modification of the SAS3D/SLUMPY fuel motion model to include among the forces acting on the upper fuel pin stub, the pressure difference between the gas plenum and the lower end of the pin stub. Finally, the loss-of-flow analysis was performed for several values of the sodium void worth to assess the sensitivity of the results to the magnitude of this reactivity feedback component.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1979 with total page 748 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Case for Integral Core disruptive Accident Analysis written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Integral analysis is an approach used at the Los Alamos National Laboratory to cope with the broad multiplicity of accident paths and complex phenomena that characterize the transition phase of core-disruptive accident progression in a liquid-metal-cooled fast breeder reactor. The approach is based on the combination of a reference calculation, which is intended to represent a band of similar accident paths, and associated system- and separate-effect studies, which are designed to determine the effect of uncertainties. Results are interpreted in the context of a probabilistic framework. The approach was applied successfully in two studies; illustrations from the Clinch River Breeder Reactor licensing assessment are included.

Download or read book Problems with publications related to the Clinch River Breeder Reactor Project written by United States. General Accounting Office and published by . This book was released on 1978 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Preliminary Analysis of the Transient Overpower Accident for CRBRP Final Report written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A preliminary analysis of the transient overpower accident for the Clinch River Breeder Reactor Plant (CRBRP) is presented. Several uncertainties in the analysis and the estimation of ramp rates during the transition to disassembly are discussed. The major conclusions are summarized.

Download or read book ERDA Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 780 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 1984 with total page 744 pages. Available in PDF, EPUB and Kindle. Book excerpt: