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Uncertainties in modeling and scaling in the prediction of fuel stored energy and thermal response

Description: The steady-state temperature distribution and the stored energy in nuclear fuel elements are computed by analytical methods and used to rank, in the order of importance, the effects on stored energy from statistical uncertainties in modeling parameters, in boundary and in operating conditions. An integral technique is used to calculate the transient fuel temperature and to estimate the uncertainties in predicting the fuel thermal response and the peak clad temperature during a large-break loss … more
Date: January 1, 1987
Creator: Wulff, W.
Partner: UNT Libraries Government Documents Department
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Agency update: Savannah River Plant

Description: This report summarizes activities at the Savannah River Plant, with regard to personnel, program activities, and equipment. Pinch welding procedures are discussed and progress on reclamation of 3T and SP 1030/1031 reservoirs has been detailed Gas Metal Arc welding was also investigated as a means of structural repair of reactor vessels. (FI)
Date: January 1, 1987
Creator: Eberhard, B J
Partner: UNT Libraries Government Documents Department
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Seismic fragility of nuclear power plant components: Phase 2, Motor control center, switchboard, panelboard and power supply

Description: In Phase I of the Component Fragility Program, Brookhaven National Laboratory (BNL) has developed a procedure to establish the seismic fragility of nuclear power plant equipment by use of existing test data and demonstrated its application by considering two equipment pieces. In Phase II of the program, BNL has collected additional test data, and has further advanced and is applying the methodology to determine the fragility levels of selected essential equipment categories. The data evaluation… more
Date: December 1, 1987
Creator: Bandyopadhyay, K. K.; Hofmayer, C. H.; Kassir, M. K. & Pepper, S. E.
Partner: UNT Libraries Government Documents Department
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An overview of environmental degradation of materials in nuclear power plant piping systems

Description: Piping in light water reactor (LWR) power systems is affected by several types of environmental degradation: intergranular stress corrosion cracking (IGSCC) of austenitic stainless steel piping in boiling water reactors (BWRs) has required research, inspection, and mitigation programs that will ultimately cost several billion dollars; erosion-corrosion of carbon steel piping has been observed frequently in the secondary systems of both BWRs and pressurized water reactors (PWRs); the effect of t… more
Date: August 1, 1987
Creator: Shack, W.J.
Partner: UNT Libraries Government Documents Department
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Effects of commercial cladding on the fracture behavior of pressure vessel steel plates

Description: The objective of this program is to determine the effect, if any, of stainless steel cladding upon the propagation of small surface cracks subjected to stress states similar to those produced by thermal shock conditions. Preliminary results from testing at temperatures 10/sup 0/ and 60/sup 0/C below NDT have shown that (1) a tough surface layer (cladding and/or HAZ) has arrested running flaws under conditions where unclad plates have ruptured, and (2) the residual load-bearing capacity of clad … more
Date: January 1, 1987
Creator: Iskander, S.K.; Alexander, D.J.; Bolt, S.E.; Cook, K.V.; Corwin, W.R.; Oland, B.C. et al.
Partner: UNT Libraries Government Documents Department
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Managing the effects of aging and reliability improvement

Description: Over recent years the electric power generating community has acknowledged the importance of the aging process on plant safety and availability. To cope with time-dependent degradation phenomenon that can affect active as well as passive components and lead to unacceptable, unanticipated failures requires research into the mechanisms of the aging process, advances in productive methods for assessing the aging impact on risk and availability, and a better understanding of power plant operations … more
Date: January 1, 1987
Creator: Hall, R.E.; Taylor, J.H. & Boccio, J.L.
Partner: UNT Libraries Government Documents Department
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Component Fragility Research Program: Phase 1, Demonstration tests: Volume 1, Summary report

Description: This report describes tests performed in Phase I of the NRC Component Fragility Research Program. The purpose of these tests was to demonstrate procedures for characterizing the seismic fragility of a selected component, investigating how various parameters affect fragility, and finally using test data to develop practical fragility descriptions suitable for application in probabilistic risk assessments. A three-column motor control center housing motor controllers of various types and sizes as… more
Date: August 1, 1987
Creator: Holman, G. S.; Chou, C. K.; Shipway, G. D. & Glozman, V.
Partner: UNT Libraries Government Documents Department
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Safety and licensing of MHTGR (Modular High Temperature Gas Cooled Reactor)

Description: The Modular High Temperature Gas Cooled Reactor (MHTGR) design meets stringent top-level regulatory and user safety requirements that require that the normal and off-normal operation of the plant not disturb the public's day-to-day activities. Quantitative, top-level regulatory criteria have been specified from US NRC and EPA sources to guide the design. The user/utility group has further specified that these criteria be met at the plant boundary. The focus of the safety approach has then been … more
Date: July 1, 1987
Creator: Silady, F.A.; Millunzi, A.C.; Kelley, A.P. Jr. & Cunliffe, J.
Partner: UNT Libraries Government Documents Department
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Safety and licensing for small and medium power reactors

Description: Proposed new concepts for small and medium power reactors differ substantially from traditional Light Water Reactors (LWRs). Although designers have a large base of experience in safety and licensing, much of it is not relevant to new concepts. It can be a disadvantage if regulators apply LWR rules directly. A fresh start is appropriate. The extensive interactions between industry, regulators, and the public complicates but may enhance safety. It is basic to recognize the features that distingu… more
Date: January 1, 1987
Creator: Trauger, D.B.
Partner: UNT Libraries Government Documents Department
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A computer program to determine the specific power of prismatic-core reactors

Description: A computer program has been developed to determine the maximum specific power for prismatic-core reactors as a function of maximum allowable fuel temperature, core pressure drop, and coolant velocity. The prismatic-core reactors consist of hexagonally shaped fuel elements grouped together to form a cylindrically shaped core. A gas coolant flows axially through circular channels within the elements, and the fuel is dispersed within the solid element material either as a composite or in the form … more
Date: May 1, 1987
Creator: Dobranich, D.
Partner: UNT Libraries Government Documents Department
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Vibrational experiments at the HDR (Heissdampfreaktor): SHAG results and planning for SHAM

Description: As part of the second phase of vibrational/earthquake investigations at the HDR (Heissdampfreaktor) Test Facility in Kahl/Main, FRG, high-level shaker tests (SHAG) were performed during June and July 1986 using a coast-down shaker capable of generating 1000 tons of force. The purpose of these experiments was to investigate full-scale structural response, soil/structure interaction, and piping and equipment response under strong excitation conditions. While global safety considerations imposed l… more
Date: January 1, 1987
Creator: Kot, C.A.; Malcher, L. & Steinhilber, H.
Partner: UNT Libraries Government Documents Department
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Evaluation of the potential for fish passage through the N Reactor and the Hanford generating project discharges

Description: The potential for juvenile downstream-migrating salmonids to encounter both the Hanford Generating Project (HGP) and N Reactor discharges was evaluated. Three general scenarios were assessed for fish exposure: (1) HGP plume centerline passage followed by N Reator plum centerline passage, (2) HGP plume centerline passage including intersection with the N Reactor plume, and (3) noncenterline plume passage through the edge of first the HGP and then the N Reactor plume. It is highly unlikely that a… more
Date: September 1, 1987
Creator: Dauble, D. D.; Vail, L. W. & Neitzel, D. A.
Partner: UNT Libraries Government Documents Department
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Incorporating ''fuzzy'' data and logical relations in the design of expert systems for nuclear reactors

Description: This paper applies the method of assigning probability in Dempster-Shafer Theory (DST) to the components of rule-based expert systems used in the control of nuclear reactors. Probabilities are assigned to premises, consequences, and rules themselves. This paper considers how uncertainty can propagate through a system of Boolean equations, such as fault trees or expert systems. The probability masses assigned to primary initiating events in the expert system can be derived from observing a nucle… more
Date: 1987~
Creator: Guth, Michael A. S.
Partner: UNT Libraries Government Documents Department
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Present and future nuclear power generation as a reflection of individual countries' resources and objectives

Description: The nuclear reactor industry has been in a state of decline for more than a decade in most of the world. The reasons are numerous and often unique to the energy situation of individual countries. Two commonly cited issues influence decisions relating to construction of reactors: costs and the need, or lack thereof, for additional generating capacity. Public concern has ''politicized'' the nuclear industry in many non-communist countries, causing a profound effect on the economics of the option.… more
Date: June 26, 1987
Creator: Borg, I.Y.
Partner: UNT Libraries Government Documents Department
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Abstracts of Phase 1 awards, (fiscal year) 1987

Description: Contained in this booklet are abstracts of the Phase I awards made in Fiscal Year 1987 under the Small Business Innovation Research (SBIR) program in the Department of Energy (DOE). The program is designed for implementation in a three-phase process, with Phase I determining the scientific or technical merit and feasibility of ideas proposed for investigation. The period of performance in this initial phase is relatively brief, typically about 6 months, and the awards are limited to $50,000. Ph… more
Date: January 1, 1987
Partner: UNT Libraries Government Documents Department
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SAFT-UT utilities: Guide to SAFT-UT principles and conventions

Description: This guide, the Guide to SAFT-UT (Synthetic Aperture Focusing Technique-Ultrasonic Testing), Principles and Conventions, is intended to provide the user with an overall background for practical implementation of SAFT-UT and the associated software utilities. It is not intended to exhaustively cover each related item, but rather to supply information from theory and experience that will assist the serious user in exploiting the robust nature of the SAFT technology. Chapter 1 gives an introductor… more
Date: October 1, 1987
Creator: Hall, T.E.
Partner: UNT Libraries Government Documents Department
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An overview of plutonium-238 decontamination and decommissioning (D and D) projects at Mound

Description: Mound is currently decontaminating for restricted reuse and/or decommissioning for conditional release four major plutonium-238 contaminated facilities that contained 1700 linear feet of gloveboxes and associated equipment and services. Several thousand linear feet of external underground piping, associated tanks, and contaminated soil are being removed. Two of the facilities contain ongoing operations and will be reused for both radioactive and nonradioactive programs. Two others will be compl… more
Date: January 1, 1987
Creator: Bond, W. H.; Davis, W. P.; Draper, D. G.; Geichman, J. R.; Harris, J. C.; Jaeger, R. R. et al.
Partner: UNT Libraries Government Documents Department
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Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

Description: The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as h… more
Date: January 1, 1987
Creator: Seidensticker, R.W.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division progress report for the period April 1, 1985 to December 31, 1986

Description: This progress report summarizes the research and development efforts conducted in the Chemical Technology Division (Chem Tech) during the period April 1, 1985, through December 31, 1986. The following major areas are covered in the discussion: nuclear and chemical waste management, environmental control technology, basic science and technology, biotechnology research, transuranium-element processing, Nuclear Regulatory Commission programs, radioactive materials production, computer/engineering … more
Date: August 1, 1987
Partner: UNT Libraries Government Documents Department
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Evaluation of the /sup 252/Cf-source-driven neutron noise analysis method for measuring the subcriticality of LWR fuel storage casks

Description: The /sup 252/Cf-source-driven neutron noise analysis method was evaluated to determine if it could be used to measure the subcriticality of storage casks of burnt LWR fuel submerged in fuel storage pools, fully loaded and as they are being loaded. The motivation for this evaluation was that measurements of k/sub eff/ would provide the parameter most directly related to the criticality safety of storage cask configurations of LWR fuel and could allow proper credit for fuel burnup without relianc… more
Date: November 15, 1987
Creator: Mihalczo, J.T.
Partner: UNT Libraries Government Documents Department
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Analysis of piping response to thermal and operational transients

Description: The reactor piping system is an extremely complex three-dimensional structure. Maintaining its structural integrity is essential to the safe operation of the reactor and the steam-supply system. In the safety analysis, various transient loads can be imposed on the piping which may cause plastic deformation and possible damage to the system, including those generated from hydrodynamic wave propagations, thermal and operational transients, as well as the seismic events. At Argonne National Labora… more
Date: January 1, 1987
Creator: Wang, C. Y.
Partner: UNT Libraries Government Documents Department
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A void distribution model-flashing flow

Description: A new model for flashing flow based on wall nucleations is proposed here and the model predictions are compared with some experimental data. In order to calculate the bubble number density, the bubble number transport equation with a distributed source from the wall nucleation sites was used. Thus it was possible to avoid the usual assumption of a constant bubble number density. Comparisons of the model with the data shows that the model based on the nucleation site density correlation appears … more
Date: January 1, 1987
Creator: Riznic, J.; Ishii, M. & Afgan, N.
Partner: UNT Libraries Government Documents Department
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Handbook of software quality assurance techniques applicable to the nuclear industry

Description: Pacific Northwest Laboratory is conducting a research project to recommend good engineering practices in the application of 10 CFR 50, Appendix B requirements to assure quality in the development and use of computer software for the design and operation of nuclear power plants for NRC and industry. This handbook defines the content of a software quality assurance program by enumerating the techniques applicable. Definitions, descriptions, and references where further information may be obtained… more
Date: August 1, 1987
Creator: Bryant, J.L. & Wilburn, N.P.
Partner: UNT Libraries Government Documents Department
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