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Analysis of nuclear power plant component failures

Description: Items are shown that have caused 90% of the nuclear unit outages and/or deratings between 1971 and 1980 and the magnitude of the problem indicated by an estimate of power replacement cost when the units are out of service or derated. The funding EPRI has provided on these specific items for R and D and technology transfer in the past and the funding planned in the future (1982 to 1986) are shown. EPRI's R and D may help the utilities on only a small part of their nuclear unit outage problems. F… more
Date: January 1, 1984
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Overall plant concept for a tank-type fast reactor

Description: Japanese nuclear industries are expressing interest in the merits of the tank-type FBR as a large plant (demonstration) after JOYO (experimental, in operation) and MONJU (prototype, under construction). In response to this growing interest in a tank-type FBR demonstration plant, Hitachi has initiated a conceptual study of a 1000 MWe tank plant concept in collaboration with GE and Bechtel. Key objectives of this study have been: to select reliable and competitive tank plant concepts, with emphas… more
Date: January 1, 1984
Creator: Yamaki, Hideo; Davies, S.M. & Goodman, L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Seismic and layout design for a tank-type fast reactor

Description: Hitachi Ltd. of Japan, with the assistance of the Bechtel Group, Inc. and the General Electric Company of the US, initiated a conceptual design study of a compact tank-type LMFBR. The Bechtel work concentrated on layout of the nuclear island (NI), and its orientation with respect to the Control (CB) and Turbine (TGB) Buildings. This joint effort was carried out during 1982 and 1983 in four steps. Each step produced improvements in the design and reduced the plant size and cost. This paper descr… more
Date: June 1, 1984
Creator: Goodman, L.; Yamaki, Hideo & Davies, S.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization of nuclear reactor containment penetrations. Preliminary report

Description: 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… more
Date: June 1, 1984
Creator: Bump, T. R.; Seidensticker, R. W.; Shackelford, M. A.; Gambhir, V. K. & McLennan, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Annotated bibliography of human factors applications literature

Description: This bibliography was prepared as part of the Human Factors Technology Project, FY 1984, sponsored by the Office of Nuclear Safety, US Department of Energy. The project was conducted by Lawrence Livermore National Laboratory, with Essex Corporation as a subcontractor. The material presented here is a revision and expansion of the bibliographic material developed in FY 1982 as part of a previous Human Factors Technology Project. The previous bibliography was published September 30, 1982, as Atta… more
Date: September 30, 1984
Creator: McCafferty, D.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Public confidence in local management officials: organizational credibility and emergency behavior

Description: Confidence issues create potential risks for the public in any emergency situation. They do so because credibility and associated perceptions of legitimacy and competency of organizations are determinants of human behavior in disasters. Credibility, however, is only one of numerous factors that shape response of people or organizations to a threatening event. The purposes of this paper are to review what is known about the way in which credibility and related constructs influence emergency resp… more
Date: January 1, 1984
Creator: Sorensen, J.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Seismic Category I Structures Program

Description: The Seismic Category I Structures Program currently being carried out at the Los Alamos National Laboratory is sponsored by the Mechanical/Structural Engineering Branch, Division of Engineering Technology of the Nuclear Regulatory Commission (NRC). This project is part of a program designed to increase confidence in the assessment of Category I nuclear power plant structural behavior beyond the design limit. The program involves the design, construction, and testing of heavily reinforced concre… more
Date: January 1, 1984
Creator: Endebrock, E. G.; Dove, R. C. & Anderson, C. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Results of comparative assessment of US and Foreign Nuclear Power Plant dose experience and dose reduction programs

Description: Based on data evaluated to date it is clear that US plants have higher collective dose equivalents per reactor and per MW-y generated than most other countries. Factors which contribute to low doses include: (1) minimization of cobalt in primary system components exposed to water, (2) careful control of primary system oxygen and pH, (3) good primary system water purity to minimize corrosion product formation, (4) careful plant design, layout and component segration and shielding, (5) management… more
Date: January 1, 1984
Creator: Baum, J. W.; Horan, J. R. & Dionne, B. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of generic floor response spectra for equipment qualification for seismic loads

Description: A generic floor response spectra has been developed for use in the qualification of electrical and mechanical equipment in operating nuclear power plants. Actual PWR and BWR - Mark I structural models were used as representative of a class of structures. For each model, the stiffness properties were varied, with the same mass, so as to extend the fundamental base structure natural frequency from 2 cps to 36 cps. This resulted in fundamental mode coupled natural frequencies as low as 0.86 cps an… more
Date: October 1, 1984
Creator: Curreri, J.R. & Costantino, C.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear power plant control room operators' performance research

Description: A research program is being conducted to provide information on the performance of nuclear power plant control room operators when responding to abnormal/emergency events in the plants and in full-scope training simulators. The initial impetus for this program was the need for data to assess proposed design criteria for the choice of manual versus automatic action for accomplishing safety-related functions during design basis accidents. The program also included studies of training simulator ca… more
Date: January 1, 1984
Creator: Gray, L.H. & Haas, P.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Environmental effects on materials in operating power reactors

Description: This paper reviews several areas in which corrosion problems have occurred and what can be done to help improve future performance: BWR pipe cracking, PWR steam generators, Three Mile Island-thiosulfate contamination, secondary side problems, mechanical damage (Ginna), piping and vessel cracking, turbine cracking, and bolting. The safety and operational issues involved are listed. (DLC)
Date: September 24, 1984
Creator: Weeks, J.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 4. Evaluation of other loads and load combinations

Description: Six topical areas were covered by the Task Group on Other Dynamic Loads and Load Combinations as described below: Event Combinations - dealing with the potential simultaneous occurrence of earthquakes, pipe ruptures, and water hammer events in the piping design basis; Response Combinations - dealing with multiply supported piping with independent inputs, the sequence of combinations between spacial and modal components of response, and the treatment of high frequency modes in combination with l… more
Date: December 1, 1984
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High-speed LWR transients simulation for optimizing emergency response

Description: The purpose of computer-assisted emergency response in nuclear power plants, and the requirements for achieving such a response, are presented. An important requirement is the attainment of realistic high-speed plant simulations at the reactor site. Currently pursued development programs for plant simulations are reviewed. Five modeling principles are established and a criterion is presented for selecting numerical procedures and efficient computer hardware to achieve high-speed simulations. A … more
Date: November 19, 1984
Creator: Wulff, W.; Cheng, H.S.; Lekach, S.V.; Mallen, A.N. & Stritar, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reliability analysis of RC containment structures under combined loads

Description: This paper discusses a reliability analysis method and load combination design criteria for reinforced concrete containment structures under combined loads. The probability based reliability analysis method is briefly described. For load combination design criteria, derivations of the load factors for accidental pressure due to a design basis accident and safe shutdown earthquake (SSE) for three target limit state probabilities are presented.
Date: January 1, 1984
Creator: Hwang, H.; Reich, M. & Kagami, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Improved inter-assembly heat transfer modeling under low flow conditions for the Super System Code (SSC)

Description: The Super System Code (SSC) was developed at the Brookhaven National Laboratory (BNL) for the thermal hydraulic analysis of natural circulation transients, operational transients, and other system wide transients in nuclear power plants. SSC is a generic, best estimate code that models the in-vessel components, heat transport loops, plant protection systems and plant control systems. SSC also simulates the balance of plant when interfaced with the MINET code. SSC has been validated against both… more
Date: January 1, 1984
Creator: Horak, W.C. & Guppy, J.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Files used to generate figures and tables in the application of the SSMRP methodology to the seismic risk at the Zion Nuclear Power Plant

Description: The Seismic Safety Margins Research Program (SSMRP) was a program conducted 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. The analysis procedure was based on a state-of-the-art evaluation of then current seismic analysis and design processes, and it explicitly attempted to account for some of the uncertainties inherent in such processes. Th… more
Date: December 3, 1984
Creator: George, L.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Flux synthesis for the on-line surveillance of nuclear power plants

Description: This summary briefly describes the development of a calculational method suitable for on-line reactivity and power distribution monitoring (RPDM). Underlying the development of this calculational method is the expansion of the neutron flux in a complete set of eigenfunctions corresponding to the buckling eigenvalues of a Helmoltz equation. Expansions in such eigenfunctions have previously been used for solving reactor kinetics problems, and for analyzing reactivity and flux effects induced by r… more
Date: January 1, 1984
Creator: Difilippo, F. C.; Cacuci, D. G. & Worley, B. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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In situ calibration of nuclear plant resistance thermometers using Johnson noise. Draft

Description: Methods have been demonstrated in operating nuclear plants for the in situ calibration of resistance thermometers with agreement between measured noise temperatures and dc calibration temperatures well within these required by the plant. A comparison of the results of Johnson noise power testing results and uncertainties, the requirements for accuracy, and PRT calibration tolerances is shown. The methods use Johnson noise measurements and provide an absolute calibration independent of the prior… more
Date: January 1, 1984
Creator: Blalock, T.V.; Roberts, M.J. & Shepard, R.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of uncertainties in CRAC2 calculations: wet deposition and plume rise

Description: We have studied the sensitivity of results from the CRAC2 computer code, which predicts health impacts from a reactor-accident scenario, to uncertainties in selected meteorological models and parameters. The sources of uncertainty examined include the models for plume rise and wet deposition and the meteorological bin-sampling procedure. An alternative plume-rise model usually had little effect on predicted health impacts. In an alternative wet-deposition model, the scavenging rate depends only… more
Date: January 1, 1984
Creator: Ward, R. C.; Kocher, D. C.; Hicks, B. B.; Hosker, R. P., Jr.; Ku, J. Y. & Rao, K. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Neutron dosimetry at commercial nuclear plants. Annual report of Subtask D: TEPC feasibility

Description: This study was designed to observe the feasibility of the use by NRC licensees of the tissue equivalent proportional counter (TEPC) system as a neutron monitoring instrument. Laboratory tissue equivalent proportional counters were irradiated using /sup 252/Cf sources at NBS and PNL and were irradiated inside containment of four operating nuclear power plants (two boiling water reactors and two pressurized water reactors). On the average, neutron dose-equivalent rates determined using the TEPC w… more
Date: June 1, 1984
Creator: Cummings, F.M.; Endres, G.W.R.; McDonald, J.C. & Brackenbush, L.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Regulatory trends and practices related to nuclear reactor decommissioning

Description: In the next several decades, the electric utility industry will be faced with the retirement of 50,000 megawatts (mW) of nuclear capacity. Responsibility for the financial and technical burdens this activity entails has been delegated to the utilities operating the reactors. However, the operators will have to perform the tasks of reactor decommissioning within the regulatory environment dictated by federal, state and local regulations. The purpose of this paper is to highlight some of the curr… more
Date: January 1, 1984
Creator: Cantor, R. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings

Description: On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the … more
Date: August 1, 1984
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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CONCEPT computer code

Description: CONCEPT is a computer code that will provide conceptual capital investment cost estimates for nuclear and coal-fired power plants. The code can develop an estimate for construction at any point in time. Any unit size within the range of about 400 to 1300 MW electric may be selected. Any of 23 reference site locations across the United States and Canada may be selected. PWR, BWR, and coal-fired plants burning high-sulfur and low-sulfur coal can be estimated. Multiple-unit plants can be estimated… more
Date: January 1, 1984
Creator: Delene, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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