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Advanced Test Reactor Atr Facility 10cfr830 Safety Basis Related To Facility Experiments
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Book Synopsis Advanced Test Reactor (ATR) Facility 10CFR830 Safety Basis Related to Facility Experiments by :
Download or read book Advanced Test Reactor (ATR) Facility 10CFR830 Safety Basis Related to Facility Experiments written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Test Reactor (ATR), a DOE Category A reactor, was designed to provide an irradiation test environment for conducting a variety of experiments. The ATR Safety Analysis Report, determined by DOE to meet the requirements of 10 CFR 830, Subpart B, provides versatility in types of experiments that may be conducted. This paper addresses two general types of experiments in the ATR facility and how safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore this type of experiment is addressed with more detail in the safety basis. This allows individual safety analyses for these experiments to be more routine and repetitive. The second type of experiment is less defined and is permitted under more general controls. Therefore, individual safety analyses for the second type of experiment tend to be more unique from experiment to experiment. Experiments are also discussed relative to "major modifications" and DOE-STD-1027-92. Application of the USQ process to ATR experiments is also discussed.
Book Synopsis Advanced Test Reactor Safety Basis Upgrade Lessons Learned Relative to Design Basis Verification and Safety Basis Management by :
Download or read book Advanced Test Reactor Safety Basis Upgrade Lessons Learned Relative to Design Basis Verification and Safety Basis Management written by and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The reactor also provides other irradiation services such as radioisotope production. The ATR and its support facilities are located at the Test Reactor Area of the Idaho National Engineering and Environmental Laboratory (INEEL). An audit conducted by the Department of Energy's Office of Independent Oversight and Performance Assurance (DOE OA) raised concerns that design conditions at the ATR were not adequately analyzed in the safety analysis and that legacy design basis management practices had the potential to further impact safe operation of the facility. 1 The concerns identified by the audit team, and issues raised during additional reviews performed by ATR safety analysts, were evaluated through the unreviewed safety question process resulting in shutdown of the ATR for more than three months while these concerns were resolved. Past management of the ATR safety basis, relative to facility design basis management and change control, led to concerns that discrepancies in the safety basis may have developed. Although not required by DOE orders or regulations, not performing design basis verification in conjunction with development of the 10 CFR 830 Subpart B upgraded safety basis allowed these potential weaknesses to be carried forward. Configuration management and a clear definition of the existing facility design basis have a direct relation to developing and maintaining a high quality safety basis which properly identifies and mitigates all hazards and postulated accident conditions. These relations and the impact of past safety basis management practices have been reviewed in order to identify lessons learned from the safety basis upgrade process and appropriate actions to resolve possible concerns with respect to the current ATR safety basis. The need for a design basis reconstitution program for the ATR has been identified along with the use of sound configuration management principles in order to support safe and efficient facility operation.
Book Synopsis Safety Assurance for Irradiating Experiments in the Advanced Test Reactor by : S. B. Grover
Download or read book Safety Assurance for Irradiating Experiments in the Advanced Test Reactor written by S. B. Grover and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR), located at the Idaho National Engineering and Environmental Laboratory (INEEL), was specifically designed to provide a high neutron flux test environment for conducting a variety of experiments. This paper addresses the safety assurance process for two general types of experiments conducted in the ATR facility and how the safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore, this type of experiment is addressed in more detail in the ATR safety basis. This allows the individual safety analysis for this type of experiment to be more standardized. The second type of experiment is defined in more general terms in the ATR safety basis and is permitted under more general controls. Therefore, the individual safety analysis for the second type of experiment tends to be more unique and is tailored to each experiment.
Book Synopsis Advanced Test Reactor Critical Facility Safety Analysis Report by : E. E. Burdick
Download or read book Advanced Test Reactor Critical Facility Safety Analysis Report written by E. E. Burdick and published by . This book was released on 1964 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project by :
Download or read book Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, "Program and Project Management for the Acquisition of Capital Assets," safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, "Facility Safety," and the expectations of DOE-STD-1189-2008, "Integration of Safety into the Design Process," provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.
Book Synopsis 10 CFR 830 Major Modification Determination for Advanced Test Reactor RDAS and LPCIS Replacement by :
Download or read book 10 CFR 830 Major Modification Determination for Advanced Test Reactor RDAS and LPCIS Replacement written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The replacement of the ATR Control Complex's obsolete computer based Reactor Data Acquisition System (RDAS) and its safety-related Lobe Power Calculation and Indication System (LPCIS) software application is vitally important to ensure the ATR remains available to support this national mission. The RDAS supports safe operation of the reactor by providing 'real-time' plant status information (indications and alarms) for use by the reactor operators via the Console Display System (CDS). The RDAS is a computer support system that acquires analog and digital information from various reactor and reactor support systems. The RDAS information is used to display quadrant and lobe powers via a display interface more user friendly than that provided by the recorders and the Control Room upright panels. RDAS provides input to the Nuclear Engineering ATR Surveillance Data System (ASUDAS) for fuel burn-up analysis and the production of cycle data for experiment sponsors and the generation of the Core Safety Assurance Package (CSAP). RDAS also archives and provides for retrieval of historical plant data which may be used for event reconstruction, data analysis, training and safety analysis. The RDAS, LPCIS and ASUDAS need to be replaced with state-of-the-art technology in order to eliminate problems of aged computer systems, and difficulty in obtaining software upgrades, spare parts, and technical support. The major modification criteria evaluation of the project design did not lead to the conclusion that the project is a major modification. The negative major modification determination is driven by the fact that the project requires a one-for-one equivalent replacement of existing systems that protects and maintains functional and operational requirements as credited in the safety basis.
Download or read book Small Modular Reactors written by NEA. and published by . This book was released on 2016 with total page 71 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent interest in small modular reactors (SMRs) is being driven by a desire to reduce the total capital costs associated with nuclear power plants and to provide power to small grid systems. According to estimates available today, if all the competitive advantages of SMRs were realised, including serial production, optimised supply chains and smaller financing costs, SMRs could be expected to have lower absolute and specific (per-kWe) construction costs than large reactors. Although the economic parameters of SMRs are not yet fully determined, a potential market exists for this technology, particularly in energy mixes with large shares of renewables. This report assesses the size of the market for SMRs that are currently being developed and that have the potential to broaden the ways of deploying nuclear power in different parts of the world. The study focuses on light water SMRs that are expected to be constructed in the coming decades and that strongly rely on serial, factory-based production of reactor modules. In a high-case scenario, up to 21 GWe of SMRs could be added globally by 2035, representing approximately 3% of total installed nuclear capacity.
Download or read book Commercial Nuclear Power written by and published by . This book was released on with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Handbook of Vacuum Technology by : Karl Jousten
Download or read book Handbook of Vacuum Technology written by Karl Jousten and published by John Wiley & Sons. This book was released on 2016-06-14 with total page 1050 pages. Available in PDF, EPUB and Kindle. Book excerpt: This comprehensive, standard work has been updated to remain an important resource for all those needing detailed knowledge of the theory and applications of vacuum technology. The text covers the existing knowledge on all aspects of vacuum science and technology, ranging from fundamentals to components and operating systems. It features many numerical examples and illustrations to help visualize the theoretical issues, while the chapters are carefully cross-linked and coherent symbols and notations are used throughout the book. The whole is rounded off by a user-friendly appendix of conversion tables, mathematical tools, material related data, overviews of processes and techniques, equipment-related data, national and international standards, guidelines, and much more. As a result, engineers, technicians, and scientists will be able to develop and work successfully with the equipment and environment found in a vacuum.
Book Synopsis Code Requirements for Nuclear Safety-related Concrete Structures (ACI 349-13) and Commentary : an ACI Standards by :
Download or read book Code Requirements for Nuclear Safety-related Concrete Structures (ACI 349-13) and Commentary : an ACI Standards written by and published by . This book was released on 2014 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Storage of Spent Nuclear Fuel by : International Atomic Energy Agency
Download or read book Storage of Spent Nuclear Fuel written by International Atomic Energy Agency and published by . This book was released on 2021-04-30 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is a revision by amendment of IAEA Safety Standards Series No. SSG-15 and provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facility and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods beyond the original design lifetime of the storage facility that have become necessary owing to delays in the development of disposal facilities and the reduction in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup. Guidance is provided on all stages in the lifetime of a spent fuel storage facility, from planning through siting and design to operation and decommissioning. The revision was undertaken by amending, adding and/or deleting specific paragraphs addressing recommendations and findings from studying the accident at the Fukushima Daiichi nuclear power plant in Japan.
Book Synopsis Uncertainty Underground by : Allison Macfarlane
Download or read book Uncertainty Underground written by Allison Macfarlane and published by MIT Press. This book was released on 2006 with total page 457 pages. Available in PDF, EPUB and Kindle. Book excerpt: Experts from science, industry, and government discuss the unresolved scientific and technical issues surrounding the Yucca Mountain site as a geologic repository for high-level nuclear waste.
Author :The Law The Law Library Publisher :Createspace Independent Publishing Platform ISBN 13 :9781722327873 Total Pages :36 pages Book Rating :4.3/5 (278 download)
Book Synopsis Human Reliability Program (Us Department of Energy Regulation) (Doe) (2018 Edition) by : The Law The Law Library
Download or read book Human Reliability Program (Us Department of Energy Regulation) (Doe) (2018 Edition) written by The Law The Law Library and published by Createspace Independent Publishing Platform. This book was released on 2018-07-03 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: Human Reliability Program (US Department of Energy Regulation) (DOE) (2018 Edition) The Law Library presents the complete text of the Human Reliability Program (US Department of Energy Regulation) (DOE) (2018 Edition). Updated as of May 29, 2018 DOE is amending its regulation concerning the Human Reliability Program (HRP). This regulation provides the policies and procedures to ensure that individuals who occupy positions affording unescorted access to certain nuclear materials, nuclear explosive devices, facilities and programs meet the highest standards of reliability and physical and mental suitability. The revisions include some clarification of the procedures and burden of proof applicable in certification review hearings, the addition and modification of certain definitions, and a clear statement that a security concern can be reviewed pursuant to the HRP regulation in addition to the DOE regulations for determining eligibility for access to classified matter or special nuclear material. These revisions are intended to provide better guidance to HRP-certified individuals and to ensure consistency in HRP decision making. This book contains: - The complete text of the Human Reliability Program (US Department of Energy Regulation) (DOE) (2018 Edition) - A table of contents with the page number of each section
Download or read book Program Summary Report written by and published by . This book was released on 1979 with total page 98 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The State of the Laboratory written by and published by . This book was released on 1988 with total page 106 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Safety of Nuclear Power Plants by : International Atomic Energy Agency
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.
