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Book ATR ETR Reactor Safety Appraisal

Download or read book ATR ETR Reactor Safety Appraisal written by R. E. Oswald and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: During February and March 1980, the annual reactor safety appraisal of the Advanced Test Reactor (ATR) and the Engineering Test Reactor (ETR) was conducted by the Nuclear Safety Branch of the Safety Division of EG&G Idaho., Inc.

Book Nuclear Safety

Download or read book Nuclear Safety written by and published by . This book was released on 1990 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book LOFT Annual Reactor Safety Appraisal

Download or read book LOFT Annual Reactor Safety Appraisal written by R. E. Oswald and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: During July and August 1982, the annual reactor safety appraisal of the LOFT (Loss-of-Fluid-Test) Facility was conducted by the Technical Safety Support Division of EG&G Idaho, Inc., per the requirements of DOE (Department of Energy), ID (Idaho Operations Office), and EG&G.

Book Review and Updates of the Risk Assessment for Advanced Test Reactor Operations for Operating Events and Experience

Download or read book Review and Updates of the Risk Assessment for Advanced Test Reactor Operations for Operating Events and Experience written by and published by . This book was released on 1996 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annual or biannual reviews of the operating history of the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory (INEL) have been conducted for the purpose of reviewing and updating the ATR probabilistic safety assessment (PSA) for operating events and operating experience since the first compilation of plant- specific experience data for the ATR PSA which included data for operation from initial power operation in 1969 through 1988. This technical paper briefly discusses the means and some results of these periodic reviews of operating experience and their influence on the ATR PSA.

Book Safety Assurance for Irradiating Experiments in the Advanced Test Reactor

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 Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1989 with total page 624 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Radioactive Waste Management

Download or read book Radioactive Waste Management written by and published by . This book was released on 1981 with total page 520 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Safety Issues at the DOE Test and Research Reactors

Download or read book Safety Issues at the DOE Test and Research Reactors written by National Research Council (U.S.). Committee to Assess Safety and Technical Issues at DOE Reactors and published by National Academies. This book was released on 1988 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book LOFT Annual Reactor Safety Appraisal

Download or read book LOFT Annual Reactor Safety Appraisal written by R. E. Oswald and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: During September and October 1980, the annual reactor safety appraisal of the LOFT (Loss of Fluid Test) Reactor was conducted by the Safety Division of EG&G Idaho, Inc., per the requirements of DOE (Department of Energy), ID (Idaho Operations Office), and EG&G...The findings of this appraisal indicate that LOFT was in compliance with the applicable requirements in all areas reviewed. Three recommendations for improvements are made...

Book Advanced Test Reactor Critical Facility Safety Analysis Report

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 Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 654 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.

Book Advanced Test Reactor  ATR  Facility 10CFR830 Safety Basis Related to Facility Experiments

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 Safety Assurance for ATR Irradiations

Download or read book Safety Assurance for ATR Irradiations written by S. Blaine Grover and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL) is the world's premiere test reactor for performing high fluence, large volume, irradiation test programs. The ATR has many capabilities and a wide variety of tests are performed in this truly one of a kind reactor, including isotope production, simple self-contained static capsule experiments, instrumented/controlled experiments, and loop testing under pressurized water conditions. Along with the five pressurized water loops, ATR may also have gas (temperature controlled) lead experiments, fuel boosted fast flux experiments, and static sealed capsules all in the core at the same time. In addition, any or all of these tests may contain fuel or moderating materials that can affect reactivity levels in the ATR core. Therefore the safety analyses required to ensure safe operation of each experiment as well as the reactor itself are complex. Each test has to be evaluated against stringent reactor control safety criteria, as well as the effects it could have on adjacent tests and the reactor as well as the consequences of those effects. The safety analyses of each experiment are summarized in a document entitled the Experiment Safety Assurance Package (ESAP). The ESAP references and employs the results of the reactor physics, thermal, hydraulic, stress, seismic, vibration, and all other analyses necessary to ensure the experiment can be irradiated safely in the ATR. The requirements for reactivity worth, chemistry compatibilities, pressure limitations, material issues, etc. are all specified in the Technical Safety Requirements and the Upgraded Final Safety Analysis Report (UFSAR) for the ATR. This paper discusses the ESAP process, types of analyses, types of safety requirements and the approvals necessary to ensure an experiment can be safely irradiated in the ATR.

Book Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade

Download or read book Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade written by R. T. McCracken and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The regulatory requirement to develop an upgraded safety basis for a DOE nuclear facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830).1 Subpart B of 10 CFR 830, "Safety Basis Requirements," requires acontractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, 2003 an upgraded facility safety basis that meets the revised requirements.110 CFR 830 identifies Nuclear Regulatory Commission (NRC) Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants"2 as a safe harbor methodology for preparation of a DOE reactor documented safety analysis (DSA). The regulation also allows for use of a graded approach. This report presents the methodology thatwas developed for preparing the reactor accident analysis portion of the Advanced Test Reactor Critical Facility (ATRC) upgraded DSA. The methodology was approved by DOE for developing the ATRC safety basis as an appropriate application of a graded approach to the requirements of 10 CFR 830.

Book Monthly Catalogue  United States Public Documents

Download or read book Monthly Catalogue United States Public Documents written by and published by . This book was released on 1994-10 with total page 756 pages. Available in PDF, EPUB and Kindle. Book excerpt: