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Dose reduction at nuclear power plants

Description: The collective dose equivalent at nuclear power plants increased from 1250 rem in 1969 to nearly 54,000 rem in 1980. This rise is attributable primarily to an increase in nuclear generated power from 1289 MW-y to 29,155 MW-y; and secondly, to increased average plant age. However, considerable variation in exposure occurs from plant to plant depending on plant type, refueling, maintenance, etc. In order to understand the factors influencing these differences, an investigation was initiated to st… more
Date: January 1, 1983
Creator: Baum, J. W. & Dionne, B. J.
Partner: UNT Libraries Government Documents Department
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Impact of inservice inspection on the reliability of nuclear piping

Description: The reliability of nuclear piping is a function of piping quality as fabricated, service loadings and environments, plus programs of continuing inspection during operation. This report presents the results of a study of the impact of inservice inspection (ISI) programs on the reliability of specific nuclear piping systems that have actually failed in service. Two major factors are considered in the ISI programs: one is the capability of detecting flaws; the other is the frequency of performing … more
Date: December 1, 1983
Creator: Woo, H.H.
Partner: UNT Libraries Government Documents Department
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Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

Description: The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the react… more
Date: December 1, 1983
Creator: Cover, L.E.; Bohn, M.P.; Campbell, R.D. & Wesley, D.A.
Partner: UNT Libraries Government Documents Department
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Guidelines for Nuclear Power Plant Safety Issue Prioritization Information Development. Supplement 2

Description: This is the third in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues (NUREG/CR-2800, Andrews et al. 1983). This report contains results of issue-specific analyses for 31 issues. Each issue was considered within the constraints of available information as of summer 1983, and two staff-weeks of labor. The results are… more
Date: December 1, 1983
Creator: Andrews, W. B.; Gallucci, R. H. V.; Konzek, G. J.; Heaberlin, S. W.; Fecht, B. A.; Allen, C. H. et al.
Partner: UNT Libraries Government Documents Department
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Handbook for value-impact assessment

Description: The basic purpose of this handbook is to document a set of systematic procedures for providing information that can be used in performing value-impact assessments of Nuclear Regulatory Commission (NRC) regulatory actions. The handbook describes a structured but flexible process for performing the assessment. Chapter 1 is an introduction to the value-impact assessment process. Chapter 2 describes the attributes most frequently affected by proposed NRC actions, provides guidance concerningthe app… more
Date: December 1, 1983
Creator: Heaberlin, S. W.; Burnham, J. B.; Gallucci, R. H. V.; Mullen, M. F.; Nesse, R. J.; Nieves, L. A. et al.
Partner: UNT Libraries Government Documents Department
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Atoms to electricity

Description: This booklet explains the basic technology of nuclear fission power reactors, the nuclear fuel cycle and the role of nuclear energy as one of the domestic energy resources being developed to help meet our national energy demand. Nuclear power accounted for some 12 percent of the US electric energy supply in 1982. In the 1990's, it is expected to become second only to coal as a source of our electric power, almost doubling its present contribution to our national electricity supply. 14 reference… more
Date: November 1, 1983
Partner: UNT Libraries Government Documents Department
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Probability problems in seismic risk analysis and load combinations for nuclear power plants

Description: This paper describes seismic risk, load combination, and probabilistic risk problems in power plant reliability, and it suggests applications of extreme value theory. Seismic risk analysis computes the probability of power plant failure in an earthquake and the resulting risk. Components fail if their peak responses to an earthquake exceed their strengths. Dependent stochastic processes represent responses, and peak responses are maxima. A Boolean function of component failures and survivals re… more
Date: January 1, 1983
Creator: George, L.L.
Partner: UNT Libraries Government Documents Department
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Safety implications of control systems

Description: The Safety Implications of Control Systems Program has three major activities in support of USI-A47. The first task is a failure mode and effects analysis of all plant systems which may potentially induce control system disturbance that have safety implications. This task has made a preliminary study of overfill events and recommended cases for further analysis on the hybrid simulator. Work continues on overcooling and undercooling. A detailed investigation of electric power network is in progr… more
Date: January 1, 1983
Creator: Smith, O.L.
Partner: UNT Libraries Government Documents Department
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HTGR applications program advanced systems. Semiannual report, October 1, 1982-March 31, 1983

Description: Work Breakdown Structure (WBS 41) activities emphasize the advanced HTGR modular reactor system (MRS) for reformer (R) and steam cycle/-cogeneration (SC/C) applications. This report describes progress in system performance for a 250-MW(t) MRS-R and a 300-MW(t) MRS-SC/C plant; it details the groundrules and parameters for the FY-83 nuclear core design and examines and compares fuel cycle economics. This report gives results from a study on decay heat removal transients for the MRS-R and MRS-SC/C… more
Date: May 1, 1983
Partner: UNT Libraries Government Documents Department
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Public acceptance of nuclear electric generation sited in energy centers

Description: What will make an acceptable future for nuclear power. We believe there are four elements: the power must be needed. The plants must be safe. The power must be economical. The disposal of nuclear waste must be assured. And, above all, the public must believe all four are true. We have completed a study in the State of Utah, with DOE support, of building a number of nuclear power plants at one location-the Nuclear Energy Center (NEC) concept. The project would deliver power to the Southwest regi… more
Date: January 1, 1983
Creator: Bauman, H.F. & Williams, J.T.
Partner: UNT Libraries Government Documents Department
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Snubber qualification and test requirements

Description: The use of snubbers for safety related piping systems has increased significantly during the last decade. A corresponding increase in snubber requirements (criteria) has also occurred. A review of these criteria indicates inconsistencies and contradictions, and reflects how rapidly knowledge and experience has been gained and applied. This study reviews and summarizes existing criteria, illustrates inconsistencies and recommends research to resolve conflicts.
Date: May 2, 1983
Creator: Onesto, A.T. & Larson, D.A.
Partner: UNT Libraries Government Documents Department
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Review of human factors in operator aids development at ORNL

Description: Three related Oak Ridge National Laboratory (ORNL) projects in the area of human factors in diagnostic aids are described. The goal of the first, sponsored by the Electric Power Research Institute (EPRI RP2184), is to provide guidance to nuclear-utility engineers in the selection and retrofit of computer-generated display systems in nuclear-plant control rooms. The goal of the second, sponsored by the Office of Research of the Nuclear Regulatory Commission (NRC), is to provide the NRC with a pr… more
Date: January 1, 1983
Creator: Sides, W.H. Jr.
Partner: UNT Libraries Government Documents Department
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Reactor vital equipment determination techniques

Description: The Reactor Vital Equipment Determination Techniques program at the Los Alamos National Laboratory is discussed. The purpose of the program is to provide the Nuclear Regulatory Commission (NRC) with technical support in identifying vital areas at nuclear power plants using a fault-tree technique. A reexamination of some system modeling assumptions is being performed for the Vital Area Analysis Program. A short description of the vital area analysis and supporting research on modeling assumption… more
Date: January 1, 1983
Creator: Bott, T.F. & Thomas, W.S.
Partner: UNT Libraries Government Documents Department
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Diffusion rates for elevated releases

Description: A search of the literature related to diffusion from elevated sources has determined that an adequate data base exists for use in developing parameterizations for estimating diffusion rates for material released from free standing stacks at nuclear power plants. A review of published data analyses indicates that a new parameterization of horizontal diffusion rates specifically for elevated releases is not likely to significantly change the magnitudes of horizontal diffusion coefficients on the … more
Date: November 1, 1983
Creator: Ramsdell, J.V.
Partner: UNT Libraries Government Documents Department
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Pit initiation resistance of ferritic stainless steels in chloride environments from 80/sup 0/ to 260/sup 0/C

Description: The pitting resistance of high-purity ferritic stainless steels has been studied by potentiodynamic anodic polarization, mechanical film-rupture (scratch) testing, and microstructural examination. The purpose has been to determine the ability of the Fe-Cr-Mo alloys to resist pit initiation at temperatures up to 260/sup 0/C in chloride environments. At temperatures exceeding about 200/sup 0/C, Cr is shown to become much more effective than Mo to enhance alloy pitting resistance. In fact, at 260/… more
Date: January 1, 1983
Creator: Cieslak, W. R. & Duquette, D. J.
Partner: UNT Libraries Government Documents Department
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Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1. [PWR; BWR]

Description: This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more system… more
Date: August 1, 1983
Creator: Osborn, R. N.; Olson, J.; Sommers, P. E.; McLaughlin, S. D.; Jackson, M. S.; Scott, W. G. et al.
Partner: UNT Libraries Government Documents Department
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Seismic analysis of piping systems subjected to independent-support excitation

Description: This paper presents a comparison of dynamic responses of piping systems subject to independent-support excitation using the response spectrum and time-history methods. The BNL finite-element computer code PSAFE2 has been used to perform all the analyses. The time-history method combines both the inertia as well as static effect on the piping responses due to independent-support excitations at each time point, thus representing the actual responses. A sample problem is analyzed subjected to two … more
Date: January 1, 1983
Creator: Subudhi, M. & Bezler, P.
Partner: UNT Libraries Government Documents Department
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SALT (System Analysis Language Translater): A steady state and dynamic systems code

Description: SALT (System Analysis Language Translater) is a lumped parameter approach to system analysis which is totally modular. The modules are all precompiled and only the main program, which is generated by SALT, needs to be compiled for each unique system configuration. This is a departure from other lumped parameter codes where all models are written by MACROS and then compiled for each unique configuration, usually after all of the models are lumped together and sorted to eliminate undetermined var… more
Date: January 1, 1983
Creator: Berry, G. & Geyer, H.
Partner: UNT Libraries Government Documents Department
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Structural modelling and limit state identification for reliability analysis of RC containment structures

Description: One of the most important ingredients in the safety analysis of any structures, and particularly nuclear structures, is the selection of an analytical model for the structure and identification of the limit states. An analytical model facilitates the evaluation of the significant structural response to postulated as well as actual loads, while a limit state represents a state of undesirable structural behavior which must be identified for the reliability analysis. Also, limit states must be spe… more
Date: January 1, 1983
Creator: Chang, M.T.; Brown, P. & Hwang, H.
Partner: UNT Libraries Government Documents Department
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Interactive Rapid Dose Assessment Model (IRDAM): reactor-accident assessment methods. Vol. 2

Description: As part of the continuing emphasis on emergency preparedness, the US Nuclear Regulatory Commission (NRC) sponsored the development of a rapid dose assessment system by Pacific Northwest Laboratory (PNL). This system, the Interactive Rapid Dose Assessment Model (IRDAM) is a micro-computer based program for rapidly assessing the radiological impact of accidents at nuclear power plants. This document describes the technical bases for IRDAM including methods, models and assumptions used in calculat… more
Date: May 1, 1983
Creator: Poeton, R. W.; Moeller, M. P.; Laughlin, G. J. & Desrosiers, A. E.
Partner: UNT Libraries Government Documents Department
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Review of decision aids for nuclear-plant operators

Description: Responses to various computer-based operational aids varied widely in detail, thus forcing distillation of the salient features of many operational aids from information sources other than the initial questionnaire. These sources included technical and management presentations, technical papers and reports, personal discussions, taped responses, sales brochures, system specifications and schematics, and other documents. The data base is dynamic, not static, owing to the nature of current trends… more
Date: January 1, 1983
Creator: Kisner, R. A.
Partner: UNT Libraries Government Documents Department
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Evaluation of training programs and entry-level qualifications for nuclear-power-plant control-room personnel based on the systems approach to training

Description: This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of thos… more
Date: September 1, 1983
Creator: Haas, P M; Selby, D L; Hanley, M J & Mercer, R T
Partner: UNT Libraries Government Documents Department
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