Download or read book An Analysis of the Loss of coolant Accident in a Pressurized water Nuclear Reactor written by Alan Edward Ladieu and published by . This book was released on 1968 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Analysis of a Four Inch Small break Loss of coolant Accident in a Westinghouse Pressurized Water Reactor Using TRAC PF1 MOD1 written by Kimberley I. R. Knippel and published by . This book was released on 1988 with total page 324 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Accident Analysis for Nuclear Power Plants with Pressurized Water Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2003 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report contains practical guidance for performing accident analysis for nuclear power plants with pressurised water reactors, based on current international good practice. It covers key aspects required including selection of initiating events and acceptance criteria, computer codes and modelling assumptions, the preparation of input data, presentation of results and quality assurance.

Download or read book Relap5 analysis of a small break loss of coolant accident without emergency core cooling in a pressurized water reactor written by P. Kuan and published by . This book was released on 1984 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: A relap5 thermal-hydraulics model based on the design of the three mile island unit-2 nuclear reactor was used to calculate the pressurized water reactor behavior during an hypothesized small-break loss-of-coolant accident without emergency core cooling. the calculation was performed to help plan the united states nuclear regulatory commission's internationally sponsored severe fuel damage test program in the power burst facility. both the primary system and the secondary sides of the steam generators were modeled. the calculation gave fluid conditions and structural temperatures throughout the system. the results indicated that 2 h after the pipe break: the upper half of the fuel bundles would be partially liquefied by molten zircaloy; the thin structures (c-tubes and split tubes) inside the guide tubes and the core barrel would be partially melted, while other structures inside the reactor vessel would likely remain intact; the hydrogen generated from the oxidation of zircaloy by steam would fill the upper plenum; and the temperature of the primary system pressure boundary would remain low enough that no additional pipe failure would be expected to occur. the calculation also showed that the oxidation rate was limited by the supply of steam during the rapid oxidation of the zircaloy cladding.

Download or read book Proceedings of the U S Nuclear Regulatory Commission Water Reactor Safety Research Information Meeting written by and published by . This book was released on 1982 with total page 770 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Design basis Accident Analysis Methods For Light water Nuclear Power Plants written by Robert Martin and published by World Scientific. This book was released on 2019-02-13 with total page 717 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)

Download or read book Analysis of Loss of coolant Accident for a Fast spectrum Lithium cooled Nuclear Reactor for Space power Applications written by George E. Turney and published by . This book was released on 1972 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Generic Assessment of Delayed Reactor Coolant Pump Trip During Small Break Loss of coolant Accidents in Pressurized Water Reactors written by Brian Sheron and published by . This book was released on 1979 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Best estimate Analysis of a Loss of coolant Accident in a Four loop US PWR Using TRAC PD2 written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A 200-percent double-ended cold-leg break loss-of-coolant accident (LOCA) in a typical US pressurized water reactor (PWR) was simulated using the Transient Reactor Analysis Code (TRAC-PD2). The reactor system modeled represented a typical US PWR with four loops (three intact, one broken) and cold-leg emergency-core-cooling systems (ECCS). The finely noded TRAC model employed 440 three dimensional (r, THETA, z) vessel cells along with approximately 300 one-dimensional cells that modeled the primary system loops. The calculated peak-clad temperature of 950°K occurred during blowdown and the clad temperature excursion was terminated at 175 s, when complete core quenching occurred. Accumulator flows were initiated at 10 s, when the system pressure reached 4.08 MPa, and the refill phase ended at 36 s when the lower plenum refilled. During reflood, both bottom and falling film quench fronts were calculated.

Download or read book An Advanced Best estimate Computer Program for Pressurized Water Reactor Loss of coolant Accident Analysis written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Guidebook to Light Water Reactor Safety Analysis written by P. B. Abramson and published by CRC Press. This book was released on 1985-01-01 with total page 418 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Guidebook to Light Water Reactor Safety Analysis brings together government and expert researchers entrusted with maintaining the safety of reactors, preventing incidents, and for creating the guidelines for responding appropriately to emergency situations. It includes an overview presented by the U.S. Nuclear Regulatory Commission. One of the most relevant compendiums of its time, it's a volume of both historical and scientific significance and well worth the consideration of those currently involved with maintaining reactor safety..

Download or read book Thermal Analysis of Pressurized Water Reactors written by Long-sun Tong and published by . This book was released on 1970 with total page 326 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Estimating Loss of Coolant Accident Frequencies for the Standardized Plant Analysis Risk Models written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Nuclear Regulatory Commission maintains a set of risk models covering the U.S. commercial nuclear power plants. These standardized plant analysis risk (SPAR) models include several loss-of-coolant accident (LOCA) initiating events such as small (SLOCA), medium (MLOCA), and large (LLOCA). All of these events involve a loss of coolant inventory from the reactor coolant system. In order to maintain a level of consistency across these models, initiating event frequencies generally are based on plant-type average performance, where the plant types are boiling water reactors and pressurized water reactors. For certain risk analyses, these plant-type initiating event frequencies may be replaced by plant-specific estimates. Frequencies for SPAR LOCA initiating events previously were based on results presented in NUREG/CR-5750, but the newest models use results documented in NUREG/CR-6928. The estimates in NUREG/CR-6928 are based on historical data from the initiating events database for pressurized water reactor SLOCA or an interpretation of results presented in the draft version of NUREG-1829. The information in NUREG-1829 can be used several ways, resulting in different estimates for the various LOCA frequencies. Various ways NUREG-1829 information can be used to estimate LOCA frequencies were investigated and this paper presents two methods for the SPAR model standard inputs, which differ from the method used in NUREG/CR-6928. In addition, results obtained from NUREG-1829 are compared with actual operating experience as contained in the initiating events database.

Download or read book Reactor Safety Research Programs written by S. K. Edler and published by . This book was released on 1981 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Analysis of a Small break Loss of coolant Accident in a Pressurised Water Reactor written by Nikos C. Markatos and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book This Country s Most Expensive Light Water Reactor Safety Test Facility written by United States. General Accounting Office and published by . This book was released on 1976 with total page 190 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book An Engineering Test Program to Investigate a Loss of Coolant Accident written by T. R. Wilson and published by . This book was released on 1964 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt: