Download or read book Routine and Post accident Analysis of Nuclear Power Plant Reactor Coolant written by Eva I. Jolma and published by . This book was released on 1983 with total page 290 pages. Available in PDF, EPUB and Kindle. Book excerpt: The 1979 incident at Three Mile Island drew attention to weaknesses in the capability to obtain and analyze reactor coolant samples in an environment where the reactor core incurs significant damage. As a result, the U.S. Nuclear Regulatory Commission promulgated regulations requiring that reactor coolant analytical capabilities be upgraded so they could function in such an environment. The "upgrades" primarily involved the ability to safely obtain a representative sample within the count rate capabilities of the detection system and to deduce useful information from the analysis. Different designs and techniques were developed for fulfilling these regulatory requirements; however, the constraints in an environment of severe core damage make it very difficult to test the feasibility of specific design features and to determine the type of information that would be most useful to operators. To examine issues associated with post-accident monitoring, the Electric Power Research Institute funded a research project, the scope of which included, among other items, four specific radiological factors associated with routine and post-accident monitoring. The study of these four factors, evaluations of on-line monitoring versus grab sample analysis, count rate reduction factors obtainable by and spectral effects of variable aperture collimation, use of key radionuclides in assessing fuel pin integrity under both normal and abnormal reactor conditions, and possible spectral interferences from fission product releases at elevated core temperatures, provided the substance for this research report. A description of the four individual studies along with results are reported in four separate chapters. Aconclusions chapter is used to summarize the key findings of the research effort.
Download or read book Reactor Coolant and Associated Systems in Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 1986 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: Covers the safety design considerations for various reactor coolant and associated systems for operational states and accident conditions including the selection, sizing and reliability aspects. This includes safety systems such as emergency core cooling, residual heat removal or emergency feedwater systems.
Download or read book Safety of Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.
Download or read book Safety Evaluation Report Related to the Operation of Diablo Canyon Nuclear Power Plant Units 1 and 2 Docket Nos 50 275 and 50 323 Pacific Gas and Electric Company written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation 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 Safety Evaluation Report Related to the Operation of Sequoyah Nuclear Plant Units 1 and 2 Docket Nos 50 327 and 50 328 Tennessee Valley Authority written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1980 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Safety of Nuclear Power Reactors light Water cooled and Related Facilities written by U.S. Atomic Energy Commission and published by . This book was released on 1973 with total page 528 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Preliminary Analysis of Accidents in a Lithium cooled Space Nuclear Powerplant written by Harry W. Davison and published by . This book was released on 1970 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Loss of coolant Accident Analysis for Browns Ferry Nuclear Plant written by General Electric Company. Boiling Water Reactor Systems Division and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Power Safety written by James H. Rust and published by Elsevier. This book was released on 2013-10-22 with total page 419 pages. Available in PDF, EPUB and Kindle. Book excerpt: A concise and current treatment of the subject of nuclear power safety, this work addresses itself to such issues of public concern as: radioactivity in routine effluents and its effect on human health and the environment, serious reactor accidents and their consequences, transportation accidents involving radioactive waste, the disposal of radioactive waste, particularly high-level wastes, and the possible theft of special nuclear materials and their fabrication into a weapon by terrorists. The implementation of the defense-in-depth concept of nuclear power safety is also discussed. Of interest to all undergraduate and graduate students of nuclear engineering, this work assumes a basic understanding of scientific and engineering principles and some familiarity with nuclear power reactors
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 Safety Evaluation Report Related to the Operation of San Onofre Nuclear Generating Station Units 2 and 3 Docket Nos 50 361 and 50 362 Southern California Edison Company Et Al written by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation and published by . This book was released on 1981 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fukushima written by David Lochbaum and published by New Press, The. This book was released on 2015-02-10 with total page 350 pages. Available in PDF, EPUB and Kindle. Book excerpt: “A gripping, suspenseful page-turner” (Kirkus Reviews) with a “fast-paced, detailed narrative that moves like a thriller” (International Business Times), Fukushima teams two leading experts from the Union of Concerned Scientists, David Lochbaum and Edwin Lyman, with award-winning journalist Susan Q. Stranahan to give us the first definitive account of the 2011 disaster that led to the worst nuclear catastrophe since Chernobyl. Four years have passed since the day the world watched in horror as an earthquake large enough to shift the Earth's axis by several inches sent a massive tsunami toward the Japanese coast and Fukushima Daiichi nuclear power plant, causing the reactors' safety systems to fail and explosions to reduce concrete and steel buildings to rubble. Even as the consequences of the 2011 disaster continue to exact their terrible price on the people of Japan and on the world, Fukushima addresses the grim questions at the heart of the nuclear debate: could a similar catastrophe happen again, and—most important of all—how can such a crisis be averted?
Download or read book Loss of coolant Accident Analysis for Browns Ferry Nuclear Plant written by General Electric Company. Nuclear Engineering Division 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 Analysis of Delayed Reactor Coolant Pump Trip During Small Loss of Coolant Accidents for Westinghouse Nuclear Steam Supply Systems written by Westinghouse Nuclear Energy Systems and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Review of Monitoring Sampling and Analysis of Reactor Coolant Reactor Containment Atmosphere and Airborne Reactor Effluents in Post Accident Concentrations written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A post-implementation review has been made in NRC Region I of the post-accident sampling systems (PASS), the gaseous effluent monitors, and the provisions for sampling effluent particulates and radioiodines which were required by the NRC subsequent to the TMI-2 accident (NUREG-0737). Prefabricated PASS systems were predominant. Problems included insufficient purge times, inadequate separation of dissolved gases, excessive dilution and the accuracy of analytical techniques in the presence of interferences. Microprocessor-controlled high-range gas monitors with integral provisions for sampling particulates and radioiodines in high concentrations were widely used. Calibration information was generally insufficient for the unambiguous conversion of monitor readings to release rates for a varying postaccident mixture of radiogases. The referenced sampling guidance (ANSI-N 13.1-1969) was inappropriate for the long sampling lines customarily used. Generic research is needed to establish the behavior of particulates and radioiodines in these lines.
Download or read book Basic Safety Principles for Nuclear Power Plants written by International Nuclear Safety Advisory Group and published by . This book was released on 1999 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present report is a revision of Safety Series No. 75-INSAG-3 (1988), updating the statements made on the objectives and principles of safe design and operation for electricity generating nuclear power plants. It includes the improvements made in the safety of operating nuclear power plants and identifies the principles underlying the best current safety policies to be applied in future plants. It presents INSAG's understanding of the principles underlying the best current safety policies and practices of the nuclear power industry.
