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Containment Performance Of Prototypical Reactor Containments Subjected To Severe Accident Conditions
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Book Synopsis Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions by : E. W. Klamerus
Download or read book Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions written by E. W. Klamerus and published by DIANE Publishing. This book was released on 2000-08 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt: Addresses containment design practices and compares the 2 different material types (steel and concrete). Various failure modes are evaluated and computed in previous containment designs. Margin in steel and concrete containment was compared by designing and analyzing a set of surrogate containment. The containment chosen encompass the primary types of containment shapes and construction materials. For compatibility, each containment has an identical internal volume and design pressure and temperature. These containments are designed according to all applicable code requirements for nuclear reactor containment structures.
Book Synopsis Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions by : E. W. Klamerus
Download or read book Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions written by E. W. Klamerus and published by . This book was released on 1997-01-01 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt: Addresses containment design practices and compares the 2 different material types (steel and concrete). Various failure modes are evaluated and computed in previous containment designs. Margin in steel and concrete containment was compared by designing and analyzing a set of surrogate containment. The containment chosen encompass the primary types of containment shapes and construction materials. For compatibility, each containment has an identical internal volume and design pressure and temperature. These containments are designed according to all applicable code requirements for nuclear reactor containment structures.
Book Synopsis Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions, NUREG/CR-6433 by :
Download or read book Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions, NUREG/CR-6433 written by and published by . This book was released on 1996 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis CONTAINMENT PERFORMANCE OF PROTOTYPICAL REACTOR CONTAINMENTS SUBJECTED TO SEVERE ACCIDENT CONDITIONS , NUREG/CR-6433 SAND ACCIDENT CONDITIO by :
Download or read book CONTAINMENT PERFORMANCE OF PROTOTYPICAL REACTOR CONTAINMENTS SUBJECTED TO SEVERE ACCIDENT CONDITIONS , NUREG/CR-6433 SAND ACCIDENT CONDITIO written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions by :
Download or read book Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions written by and published by . This book was released on 1996 with total page 125 pages. Available in PDF, EPUB and Kindle. Book excerpt: In SECY-90-016, the NTRC proposed a safety goal of a conditional containment failure probability (CCFP) of 0.1 and the alternative acceptance criteria allowed for steel containments, which specifies that the stresses should not exceed ASNE Level C allowables for severe accident pressures and temperatures. In this work, the need for an equivalent criterion for concrete containments was studied. Six surrogate containments were designed and analyzed in order to compare the margins between design pressure, pressure resulting in exceedance of Level C (or yield) stress limits, and ultimate pressure. For comparability, each containment has an identical internal volume and design pressure. Results from the analysis showed margins to yield are comparable and display a similar margin for both steel and concrete containments. In addition, the margin to failure, although slightly higher in the steel containments, were also comparable. Finally, a CCFP for code design was determined based on general membrane behavior and imposing an upper bound severe accident curve developed in the DCH studies. The resulting CCFP's were less then 0.02 (or 2%) for all the surrogate containments studied, showing that these containment designs all achieved the NRC safety goal.
Book Synopsis Containment Integrity Research Program Plan by :
Download or read book Containment Integrity Research Program Plan written by and published by . This book was released on 1987 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting by :
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 1987 with total page 440 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Perspectives on Containment Performance Improvement Based on the IPEs by :
Download or read book Perspectives on Containment Performance Improvement Based on the IPEs written by and published by . This book was released on 1995 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Generic Letter 88-20, {open_quotes}Individual Plant Examination (IPE) for Severe Accident Vulnerabilities - 10CFR 50.54(f), {close_quotes} was issued by the NRC on November 23, 1988. In addition to assessing the core damage frequency from severe accidents, licensees were requested to report the results of their analyses regarding containment performance. Supplements to the Generic Letter forwarded technical insights obtained by the NRC staff through its Containment Performance Improvement (CPI) program. At this time, most of the IPEs have been submitted by the licensees. In a follow-on effort to support regulatory activities, the NRC staff with assistance from Brookhaven National Laboratory, has initiated a program involving a global examination of the containment performance results documented in the IPEs. The objective is to identify insights of potential generic safety significance relative to plant design, operation and maintenance, as well as to assess response to the previously forwarded CPI insights. The containment performance results of the IPEs are being categorized for commonalities and differences for different reactor and containment types. Preliminary results show that not only differences in plant design but also the methods, data, boundary conditions, and assumptions used in the different IPEs have a major impact on the containment performance results obtained. This paper presents preliminary results regarding the differences in containment performance observed in the IPEs and discusses some of the underlying reasons for these differences.
Book Synopsis Analysis of Containment Performance and Radiological Consequences Under Severe Accident Conditions for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory by :
Download or read book Analysis of Containment Performance and Radiological Consequences Under Severe Accident Conditions for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory written by and published by . This book was released on 1994 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt: A severe accident study was conducted to evaluate conservatively scoped source terms and radiological consequences to support the Advanced Neutron Source (ANS) Conceptual Safety Analysis Report (CSAR). Three different types of severe accident scenarios were postulated with a view of evaluating conservatively scoped source terms. The first scenario evaluates maximum possible steaming loads and associated radionuclide transport, whereas the next scenario is geared towards evaluating conservative containment loads from releases of radionuclide vapors and aerosols with associated generation of combustible gases. The third scenario follows the prescriptions given by the 10 CFR 100 guidelines. It was included in the CSAR for demonstrating site-suitability characteristics of the ANS. Various containment configurations are considered for the study of thermal-hydraulic and radiological behaviors of the ANS containment. Severe accident mitigative design features such as the use of rupture disks were accounted for. This report describes the postulated severe accident scenarios, methodology for analysis, modeling assumptions, modeling of several severe accident phenomena, and evaluation of the resulting source term and radiological consequences.
Book Synopsis Containment Performance for the Core Melt Accidents in BWRs with Mark I and Mark II Containments by :
Download or read book Containment Performance for the Core Melt Accidents in BWRs with Mark I and Mark II Containments written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Most previous risk assessment studies have assumed catastrophic failure of containments for severe accidents which are predicted to exceed the containment yield stress. This investigation analyzes the progression of a severe accident in order to develop realistic containment temperature and pressure loading, utilizes models for containment leakage estimates for the various loading histories, and assesses the expected failure modes and timing of releases for core melt accidents in Boiling Water Reactors (BWRs) with Mark I and Mark II containments. The results of the investigation indicate that leakage through the seal on the drywell head may be sufficient to prevent catastrophic failure of the containments for a wide range of hypothetical core melt scenarios. In addition, the investigation has indicated the potential for a previously inidentified failure mode (containment liner meltthrough) for Mark I containments in which a large fraction of the core is released from the vessel in a molten state. 14 refs.
Author :fib Fédération internationale du béton Publisher :fib Fédération internationale du béton ISBN 13 :9782883940536 Total Pages :140 pages Book Rating :4.9/5 (45 download)
Book Synopsis Nuclear Containments by : fib Fédération internationale du béton
Download or read book Nuclear Containments written by fib Fédération internationale du béton and published by fib Fédération internationale du béton. This book was released on 2001-01-01 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt: It was in 1978 that the former FIP (Fédération Internationale de la Précontrainte) published a state-of-art report on Containments for Nuclear Power Plants (NPPs). In 1996 the then FIP Commission 7 Concrete pressure vessels and containments discussed the necessity to up-date this document. After the merger of FIP with CEB (Comité Euro-International du Béton) into fib (fédération internationale du béton - international federation for structural concrete) had taken place in 1998, these activities were continued by a new fib Task-Group 1.3 Containment structures of fib Commission 1 Structures. The decision to update the 1978 report was kept with the intention to give a broad and well illustrated review of existing NPP containments as the most characteristic and complex building of nuclear power plants. Following the description of containments for different reactor systems the state-of-art report includes considerations on safety as the basic purpose of the containment, which underlies all design and construction aspects and necessitates a strict monitoring and inspection program during the whole life of the structure. Regulatory requirements and their evolution as well as recent developments, conceptual and technological, are presented. The report is complemented by two annexes on CD ROM giving some general information (on 160 NPPs built since 19972) and some more detailed data on six typical recent NPP containments. This work has been achieved during the years 1999 and 2000 thanks to the participation of members of fib Commission 1 and particularly of its Task Group 1.3, involving also further invited experts in the nuclear field from many countries all over the world. Comes with 1 CD
Book Synopsis Study of Light Water Reactor Containments Under Important Severe Accident Conditions by :
Download or read book Study of Light Water Reactor Containments Under Important Severe Accident Conditions written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US Nuclear Regulatory Commission has sponsored studies to develop a ''LEAKAGE-BEFORE-FAILURE'' model for use in severe accident risk assessments to provide a means of accounting for significant containment leakage prior to reaching the containment threshold pressure. Six containment types have been studied (large dry, subatmospheric, ice condenser, Mark I, II, and III). Potential leak paths through major containment penetration assemblies were investigated and upper-bound estimates of leak areas established. These leak areas may result from increasing internal pressure and degradation of nonmetallic seal materials due to severe accident conditions. This paper describes the approach and summarizes the results and conclusions of this study.
Author :OECD Nuclear Energy Agency Publisher :Nuclear Energy Agency, Organisation for Economic Co-operation and Development ; [Washington, D.C. : OECD Publications and Information Centre ISBN 13 : Total Pages :36 pages Book Rating :4.3/5 (91 download)
Book Synopsis The Role of Nuclear Reactor Containment in Severe Accidents by : OECD Nuclear Energy Agency
Download or read book The Role of Nuclear Reactor Containment in Severe Accidents written by OECD Nuclear Energy Agency and published by Nuclear Energy Agency, Organisation for Economic Co-operation and Development ; [Washington, D.C. : OECD Publications and Information Centre. This book was released on 1989 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: Dated April 1989
Book Synopsis Design of the Reactor Containment and Associated Systems for Nuclear Power Plants by : IAEA
Download or read book Design of the Reactor Containment and Associated Systems for Nuclear Power Plants written by IAEA and published by International Atomic Energy Agency. This book was released on 2019-12-09 with total page 86 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Safety Guide provides recommendations on meeting the requirements of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) relevant to reactor containment and associated systems. The publication addresses the containment structure and the systems with the functions of isolation, control and management of mass and energy releases, control and limitation of radioactive releases, and control and management of combustible gases. The Safety Guide is intended for use primarily for land based, stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat generating applications, such as for district heating or desalination.
Book Synopsis Design of the Reactor Containment and Associated Systems for Nuclear Power Plants by : IAEA
Download or read book Design of the Reactor Containment and Associated Systems for Nuclear Power Plants written by IAEA and published by International Atomic Energy Agency. This book was released on 2019-12-09 with total page 86 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Safety Guide provides recommendations on meeting the requirements of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) relevant to reactor containment and associated systems. The publication addresses the containment structure and the systems with the functions of isolation, control and management of mass and energy releases, control and limitation of radioactive releases, and control and management of combustible gases. The Safety Guide is intended for use primarily for land based, stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat generating applications, such as for district heating or desalination.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1988 with total page 1198 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Characterization of Nuclear Reactor Containment Penetrations. Preliminary Report by :
Download or read book Characterization of Nuclear Reactor Containment Penetrations. Preliminary Report written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes the survey work conducted by Argonne National Laboratory on the design and details of major penetrations in 22 nuclear power plants. The survey includes all containment types and materials in current use. It also includes details of all types of penetrations (except for electrical penetration assemblies and valves) and the seals and gaskets used in them. The report provides a test matrix for testing major penetrations and for testing seals and gaskets in order to evaluate their leakage potential under severe accident conditions.
