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The Advanced Neutron Source Safety Approach And Plans
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Book Synopsis The Advanced Neutron Source Safety Approach and Plans by :
Download or read book The Advanced Neutron Source Safety Approach and Plans written by and published by . This book was released on 1989 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source (ANS) is a user facility for all areas of neutron research proposed for construction at the Oak Ridge National Laboratory. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements (which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies) into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences. 8 refs., 2 tabs.
Book Synopsis Designing for Safety in the Conceptual Design of the Advanced Neutron Source by :
Download or read book Designing for Safety in the Conceptual Design of the Advanced Neutron Source written by and published by . This book was released on 1993 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source is a major new research facility proposed by the Department of Energy for construction over the next six years. The unique set of nuclear safety features selected to give the recently completed conceptual design a high degree of safety are identified and discussed.
Book Synopsis Report of the Advanced Neutron Source (ANS) Safety Workshop by : J. R. Buchanan
Download or read book Report of the Advanced Neutron Source (ANS) Safety Workshop written by J. R. Buchanan and published by . This book was released on 1988 with total page 321 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Safety written by and published by . This book was released on 1995 with total page 930 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Report of the Advanced Neutron Source (ANS) Safety Workshop, October 25-26, Knoxville, Tennessee by :
Download or read book Report of the Advanced Neutron Source (ANS) Safety Workshop, October 25-26, Knoxville, Tennessee written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Advanced Neutron Source (ANS) Project by :
Download or read book Advanced Neutron Source (ANS) Project written by and published by . This book was released on 1991 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report discusses the research and development, design and safety of the Advanced Neutron Source at Oak Ridge National Laboratory. (LSP).
Book Synopsis Report of the Advanced Neutron Source (ANS) Safety Workshop, Knoxville, Tennessee, October 25--26, 1988 by :
Download or read book Report of the Advanced Neutron Source (ANS) Safety Workshop, Knoxville, Tennessee, October 25--26, 1988 written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: On October 25--26, 1988, about 60 people took part in an Advanced Neutron Source (ANS) Safety Workshop, organized in cooperation with the Oak Ridge Operations (ORO) Office of the Department of Energy (DOE) and held in Knoxville, Tennessee. After a plenary session at which ANS Project staff presented status reports on the ANS design, research and development (R and D), and safety analysis efforts, the workshop broke into three working groups, each covering a different topic: Environmental and Waste Management, Applicable Regulatory Safety Criteria and Goals, and Reactor Concepts. Each group was asked to review the Project's approach to safety-related issues and to provide guidance on future reactor safety needs or directions for the Project. With the help of able chairmen, assisted by reporters and secretarial support, the working groups were extremely successful. Draft reports from each group were prepared before the workshop closed, and the major findings of each group were presented for review and discussion by the entire workshop attendance. This report contains the final version of the group reports, incorporating the results of the overall review by all the workshop participants.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Advanced Neutron Source written by and published by . This book was released on 1993 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report discusses the following on the Advanced Neutron Source: A global view; neutron research improves our lives; the challenge; the solution; neutron research; some major applications; environmental, safety, and health considerations; education; what the ANS means for local communities; and what will the ANS cost.
Book Synopsis Advanced Neutron Source (ANS) Project Progress Report FY 1992 by :
Download or read book Advanced Neutron Source (ANS) Project Progress Report FY 1992 written by and published by . This book was released on 1993 with total page 99 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report discusses project management, research and development, design, and safety at the Advanced Neutron Source facility.
Book Synopsis Advanced Neutron Source (ANS) Regulatory Requirements and Safety-related Considerations by :
Download or read book Advanced Neutron Source (ANS) Regulatory Requirements and Safety-related Considerations written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this document is to outline the safety-related considerations for Advanced Neutron Source (ANS) and, by so doing, to indicate the regulatory requirements and design considerations that must be addressed by the project in the design and during subsequent operations. As such, this document represents a road map of how the project intends to analyze and document nuclear safety concerns and design considerations that will have to be addressed by the ANS Project. As the project matures and the design becomes better defined and projected performance better understood, the safety-related considerations will also become better defined and interpreted. Appropriate safety-related analyses and documentation will be produced (e.g., preliminary and final safety analysis reports). This document summarizes the sources of applicable regulatory requirements, indicates recent policy guidance from the NRC, provides the NRC general design criteria that must be met, suggests which of the major ANS systems components are likely to be categorized as ''safety related, '' and provides descriptive material that is of safety interest and importance.
Book Synopsis Probabilistic Risk Assessment in the Design of the Advanced Neutron Source by :
Download or read book Probabilistic Risk Assessment in the Design of the Advanced Neutron Source written by and published by . This book was released on 1994 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Probabilistic risk assessment (PRA) has been used extensively in the design of the Advanced Neutron Source (ANS) reactor to safety risk and enhance availability. Design feautures incorporated to minimize risk include submerged primary coolant piping, circulation cooling capability, and dual independent and diverse shutdown systems. The recently completed Level I, Phase 1 PRA shows that the risk dominating event sequence initiator is now blockage; a program to minimize this identified risk is described.
Book Synopsis Advanced Neutron Source (ANS) Project Progress Report, FY 1991 by :
Download or read book Advanced Neutron Source (ANS) Project Progress Report, FY 1991 written by and published by . This book was released on 1992 with total page 99 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report discusses the following about the Advanced Neutron Source: Project Management; Research and Development; Fuel Development; Corrosion Loop Tests and Analyses; Thermal-Hydraulic Loop Tests; Reactor Control and Shutdown Concepts; Critical and Subcritical Experiments; Material Data, Structural Tests, and Analysis; Cold-Source Development; Beam Tube, Guide, and Instrument Development; Hot-Source Development; Neutron Transport and Shielding; I C Research and Development; Design; and Safety.
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 Assessment of the Roles of the Advanced Neutron Source Operators by :
Download or read book Assessment of the Roles of the Advanced Neutron Source Operators written by and published by . This book was released on 1995 with total page 63 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source (ANS) is unique in the extent to which human factors engineering (HFE) principles are being applied at the conceptual design stage. initial HFE accomplishments include the development of an ANS HFE program plan, operating philosophy, and functional analysis. In FY 1994, HFE activities focused on the role of the ANS control room reactor operator (RO). An operator-centered control room model was used in conjunction with information gathered from existing ANS system design descriptions and other literature to define a list of RO responsibilities. From this list, a survey instrument was developed and administered to ANS design engineers, operations management personnel at Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR), and HFIR ROs to detail the nature of the RO position. Initial results indicated that the RO will function as a high-level system supervisor with considerable monitoring, verification, and communication responsibilities. The relatively high level of control automation has resulted in a reshaping of the RO's traditional safety and investment protection roles.
Book Synopsis Reactivity Studies on the Advanced Neutron Source. [Advanced Neutron Source]. by :
Download or read book Reactivity Studies on the Advanced Neutron Source. [Advanced Neutron Source]. written by and published by . This book was released on 1990 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: An Advanced Neutron Source (ANS) with a peak thermal neutron flux of about 8.5 x 1019 m−2s−1 is being designed for condensed matter physics, materials science, isotope production, and fundamental physics research. The ANS is a new reactor-based research facility being planned by Oak Ridge National Laboratory (ORNL) to meet the need for an intense steady-state source of neutrons. The design effort is currently in the conceptual phase. A reference reactor design has been selected in order to examine the safety, performance, and costs associated with this one design. The ANS Project has an established, documented safety philosophy, and safety-related design criteria are currently being established. The purpose of this paper is to present analyses of safety aspects of the reference reactor design that are related to core reactivity events. These analyses include control rod worth, shutdown rod worth, heavy water voiding, neutron beam tube flooding, light water ingress, and single fuel element criticality. Understanding these safety aspects will allow us to make design modifications that improve the reactor safety and achieve the safety related design criteria. 8 refs., 3 tabs.
Book Synopsis Statistically Based Uncertainty Analysis for Ranking of Component Importance in the Thermal-hydraulic Safety Analysis of the Advanced Neutron Source Reactor by :
Download or read book Statistically Based Uncertainty Analysis for Ranking of Component Importance in the Thermal-hydraulic Safety Analysis of the Advanced Neutron Source Reactor written by and published by . This book was released on 1992 with total page 61 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Analytic Hierarchy Process (AHP) has been used to help determine the importance of components and phenomena in thermal-hydraulic safety analyses of nuclear reactors. The AHP results are based, in part on expert opinion. Therefore, it is prudent to evaluate the uncertainty of the AHP ranks of importance. Prior applications have addressed uncertainty with experimental data comparisons and bounding sensitivity calculations. These methods work well when a sufficient experimental data base exists to justify the comparisons. However, in the case of limited or no experimental data the size of the uncertainty is normally made conservatively large. Accordingly, the author has taken another approach, that of performing a statistically based uncertainty analysis. The new work is based on prior evaluations of the importance of components and phenomena in the thermal-hydraulic safety analysis of the Advanced Neutron Source Reactor (ANSR), a new facility now in the design phase. The uncertainty during large break loss of coolant, and decay heat removal scenarios is estimated by assigning a probability distribution function (pdf) to the potential error in the initial expert estimates of pair-wise importance between the components. Using a Monte Carlo sampling technique, the error pdfs are propagated through the AHP software solutions to determine a pdf of uncertainty in the system wide importance of each component. To enhance the generality of the results, study of one other problem having different number of elements is reported, as are the effects of a larger assumed pdf error in the expert ranks. Validation of the Monte Carlo sample size and repeatability are also documented.
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