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Aging assessment of BWR control rod drive systems

Description: This study examines the aging phenomena associated with boiling water reactor (BWR) control rod drive mechanisms (CRDMs) and assess the merits of various methods of managing this aging. Information for this study was acquired from (1) the results of a special CRDM aging questionnaire distributed to each US BWR utility, (2) a first-of-its-kind workshop held to discuss CRDM aging and maintenance concerns, (3) an analysis of Nuclear Plant Reliability Data System (NPRDS) failure cases attributed to… more
Date: January 1, 1991
Creator: Greene, R.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Identification and assessment of containment and release management strategies for a BWR Mark I containment

Description: This report identifies and assesses accident management strategies which could be important for preventing containment failure and/or mitigating the release of fission products during a severe accident in a BWR plant with a Mark 1 type of containment. Based on information available from probabilistic risk assessments and other existing severe accident research, and using simplified containment and release event trees, the report identifies the challenges a Mark 1 containment could face during t… more
Date: September 1, 1991
Creator: Lin, C. C. & Lehner, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DOE Ofice of Civilian Radioactive Waste Management Systems studies plan, fiscal years 1991 and 1992. [Appendix lists system studies with respective abstracts]

Description: The Systems Engineering Management Plan for the DOE Office of Civilian Radioactive Waste Management, which defines the systems engineering process for the Federal Radioactive Waste System (FWMS), requires that systems studies to support the integration, evaluation, and optimization of the system be identified. These studies are generally directed toward further defining system or system-element functional requirements, including interface requirements, evaluating alternative system configuratio… more
Date: August 1, 1991
Creator: Wood, T W; Haffner, D R & Fletcher, J F
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Magnet operating experience review for fusion applications

Description: This report presents a review of magnet operating experiences for normal-conducting and superconducting magnets from fusion, particle accelerator, medical technology, and magnetohydrodynamics research areas. Safety relevant magnet operating experiences are presented to provide feedback on field performance of existing designs and to point out the operational safety concerns. Quantitative estimates of magnet component failure rates and accident event frequencies are also presented, based on fiel… more
Date: November 1, 1991
Creator: Cadwallader, L.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An analysis of molten-corium-induced failure of drain pipes in BWR Mark 2 containments

Description: This study has focused on mechanistic simulation and analysis of potential failure modes for inpedestal drywell drain pipes in the Limerick boiling water reactor (BWR) Mark 2 containment. Physical phenomena related to surface tension breakdown, heatup, melting, ablation, crust formation and failure, and core material relocation into drain pipes with simultaneous melting of pipe walls were modeled and analyzed. The results of analysis have been used to assess the possibility of drain pipe failur… more
Date: January 1, 1991
Creator: Taleyarkhan, R. P. & Podowski, M. Z.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analytical simulation of nonlinear response to seismic test excitations of HDR-VKL piping system

Description: Dynamic tests with simulated earthquake excitation (SHAM) were performed during April--May 1988 on the Versuchskreislauf (VKL) piping system at the Heissdampfreaktor (HDR) Test Facility in Kahl/Main, Federal Republic of Germany. The major objectives of these tests were to study the behavior of a full-scale in-plant piping system subjected to a range of seismic excitation levels (from design levels to those that might induce either failure of pipe supports or plasticity in the pipe runs) and to … more
Date: January 1, 1991
Creator: Srinivasan, M.G.; Kot, C.A. (Argonne National Lab., IL (United States)) & Mojtahed, M. (Purdue Univ., Hammond, IN (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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BWR stability analysis at Brookhaven National Laboratory

Description: Following the unexpected, but safely terminated, power and flow oscillations in the LaSalle-2 Boiling Water Reactor (BWR) on March 9, 1988, the Nuclear Regulatory Commission (NRC) Offices of Nuclear Reactor Regulation (NRR) and of Analysis and Evaluation of Operational Data (AEOD) requested that the Office of Nuclear Regulatory Research (RES) carry out BWR stability analyses, centered around fourteen specific questions. Ten of the fourteen questions address BWR stability issues in general and a… more
Date: January 1, 1991
Creator: Wulff, W.; Cheng, H.S.; Mallen, A.N. & Rohatgi, U.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of nuclear materials accounting for international safeguards: The past, the present, the future

Description: Nuclear materials accountancy was introduced as a primary safeguards measure in international safeguards from the inception of the EURATOM safeguards directorate in 1959 and IAEA safeguards in 1961 with the issuance of INFCIRC 26. As measurement technology evolved and safeguarded facilities increased in both number and size, measurement methodology requirements increased as reflected in INFCIRC 66 (Rev 2.) in 1968 and later in INFCIRC 153 in 1972. Early measurements relied heavily on chemical a… more
Date: January 1, 1991
Creator: Markin, J. T.; Augustson, R. H.; Eccleston, G. W. & Hakkila, E. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Firewater system inadvertent actuation frequency

Description: The purpose of this analysis was to determine generic and plant-specific firewater inadvertent actuation frequencies for wetpipe and preaction firewater systems at the Advanced Test Reactor (ATR). Firewater systems of both kinds are installed throughout the ATR facility. When installed for the protection of reactor equipment, firewater systems may also adversely affect the equipment they are meant to protect. This occurs when inadvertent actuation of a firewater system causes wetting and subseq… more
Date: August 1, 1991
Creator: Schroeder, J. A. & Eide, S. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Auxiliary feedwater system risk-based inspection guide for the Byron and Braidwood nuclear power plants

Description: In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC fo… more
Date: July 1, 1991
Creator: Moffitt, N.E. & Gore, B.F.: Vo, T.V. (Pacific Northwest Lab., Richland, WA (USA))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Reactor Instrumentation and Control Reliability and Risk Assessment

Description: Advanced nuclear power reactors will used different approaches to achieving a higher level of safety than the first generation. One approach used the technological developments in computation and electronics in the form of digital instrumentation and control (I C) to enhance the reliability, and accuracy of information for plant control, responding to the information, and controlling the plant and its systems under normal and upset environments in various states of degradation. Evaluating the r… more
Date: January 1, 1991
Creator: Fullwood, R.; Gunther, W.; Valente, J. & Azarm, M. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of electronic component failures using high-density radiography

Description: The exceptional resolution and nondestructive nature of microfocus radiography has proven to be extremely useful in the diagnosis of electronic component failures, particularly when the components are contained in sealed or encapsulated assemblies. An epoxy-encapsulated NTC thermistor and an epitaxial silicon P-N junction photodetector are examples of discrete devices in which the cause of failure was correctly hypothesized directly from a radiographic image. Subsequent destructive physical exa… more
Date: November 1, 1991
Creator: Tuohig, W.D. & Potter, T.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Towards the development of multilevel-multiagent diagnostic aids. [Root-cause analysis]

Description: Presented here is our methodology for developing automated aids for diagnosing faults in complex systems based on research at the Pacific Northwest Laboratory (PNL) for the US Department of Energy and the US Nuclear Regulatory Commission. We have designed these aids as multilevel-multiagent diagnostic aids based on principles that should be generally applicable to any complex system. Our research in fault diagnosis at PNL grew out of our work in root-cause analysis (RCA). Our approach consists … more
Date: September 1, 1991
Creator: Stratton, R.C. & Jarrell, D.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Screening dynamic evaluation of SRS cooling water line

Description: The production reactors at the Savannah River Site (SRS) have been shut down due to perceived safety concerns. A major concern is the seismic integrity of the plant. A comprehensive program is underway to assess the seismic capacity of the existing systems and components and to upgrade them to acceptable levels. The evaluation of the piping systems at the SRS is a major element of this program. Many of the piping systems at the production reactors were designed without performing dynamic analys… more
Date: January 1, 1991
Creator: Bezler, P.; Shteyngart, S. & Breidenbach, G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Generic risk insights for General Electric boiling water reactors

Description: A methodology has been developed to extract generic risk-based information from probabilistic risk assessments (PRAs) of General Electric boiling water rectors and applying the insights gained to plants that have not been subjected to a PRA. The available risk assessments (six plants) were examined to identify the most probable, i.e., dominant accident sequences at each plants. The goal was to include all sequences which represented at least 80% of core damage frequency. If the same plant speci… more
Date: May 1991
Creator: Travis, R.; Taylor, J. & Chung, J. (Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Activities of the Oil Implementation Task Force, December 1990--February 1991; Contracts for field projects and supporting research on enhanced oil recovery, April--June 1990

Description: The Oil Implementation Task Force was appointed to implement the US DOE's new oil research program directed toward increasing domestic oil production by expanded research on near- or mid-term enhanced oil recovery methods. An added priority is to preserve access to reservoirs that have the largest potential for oil recovery, but that are threatened by the large number of wells abandoned each year. This report describes the progress of research activities in the following areas: chemical floodin… more
Date: March 1, 1991
Creator: Tiedemann, H.A. (ed.) (USDOE Bartlesville Project Office, OK (USA))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reliability evaluation of the Savannah River reactor leak detection system

Description: The Savannah River Reactors have been in operation since the mid-1950's. The primary degradation mode for the primary coolant loop piping is intergranular stress corrosion cracking. The leak-before-break (LBB) capability of the primary system piping has been demonstrated as part of an overall structural integrity evaluation. One element of the LBB analyses is a reliability evaluation of the leak detection system. The most sensitive element of the leak detection system is the airborne tritium mo… more
Date: January 1, 1991
Creator: Daugherty, W.L.; Sindelar, R.L. (Westinghouse Savannah River Co., Aiken, SC (USA)) & Wallace, I.T. (Westinghouse Electric Corp., Pittsburgh, PA (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A time-dependent event tree technique for modelling recovery operations

Description: The development of a simplified time dependent event tree methodology is presented. The technique is especially applicable to describe recovery operations in nuclear reactor accident scenarios initiated by support system failures. The event tree logic is constructed using time dependent top events combined with a damage function that contains information about the final state time behavior of the reactor core. Both the failure and the success states may be utilized for the analysis. The method … more
Date: January 1, 1991
Creator: Kohut, P. & Fitzpatrick, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Accident simulation and consequence analysis in support of MHTGR safety evaluations

Description: This paper summarizes research performed at Oak Ridge National Laboratory (ORNL) to assist the Nuclear Regulatory Commission (NRC) in preliminary determinations of licensability of the US Department of Energy (DOE) reference design of a standard modular high-temperature gas-cooled reactor (MHTGR). The work described includes independent analyses of core heatup and steam ingress accidents, and the reviews and analyses of fuel performance and fission product transport technology.
Date: January 1, 1991
Creator: Ball, S. J.; Wichner, R. P.; Smith, O. L.; Conklin, J. C. (Oak Ridge National Lab., TN (United States)) & Barthold, W. P. (Barthold Associates, Inc., Knoxville, TN (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Loss of shutdown margin during PWR refueling

Description: A study has been carried out of the frequency and consequences of misloading fresh fuel assemblies during the reloading of a pressurized water reactor. The consequences were in terms of losing the required shutdown margin and inadvertent criticality. The calculations used a model of a Combustion Engineering reactor and considered different patterns of fresh fuel clustered together which would be the result of multiple operator errors. The fresh fuel had a high U-235 enrichment and was assumed t… more
Date: January 1, 1991
Creator: Diamond, D. J. & Hsu, Chia-Jung.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Investigation of breached depleted UF sub 6 cylinders

Description: In June 1990, during a three-site inspection of cylinders being used for long-term storage of solid depleted UF{sub 6}, two 14-ton steel cylinders at Portsmouth, Ohio, were discovered with holes in the barrel section of the cylinders. Both holes, concealed by UF{sub 4} reaction products identical in color to the cylinder coating, were similarly located near the front stiffening ring. The UF{sub 4} appeared to have self-sealed the holes, thus containing nearly all of the uranium contents. Martin… more
Date: September 1, 1991
Creator: Barber, E. J.; Butler, T. R.; DeVan, J. H.; Googin, J. M.; Taylor, M. S.; Dyer, R. H. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Use of probabilistic safety analyses in severe accident management

Description: An important consideration in the development and assessment of severe accident management strategies is that while the strategies are often built on the knowledge base of Probabilistic Safety Analyses (PSA), they must be interpretable and meaningful in terms of the control room indicators. In the following, the relationships between PSA and severe accident management are explored using ex-vessel accident management at a PWR ice-condenser plant as an example. 2 refs., 1 fig., 3 tabs.
Date: January 1, 1991
Creator: Neogy, P. & Lehner, J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

On-line process failure diagnosis: The necessity and a comparative review of the methodologies

Description: Three basic approaches to process failure management are defined and discussed to elucidate the role of diagnosis in the operation of nuclear power plants. The rationale for the necessity of diagnosis is given from various perspectives. A comparative review of some representative diagnostic methodologies is presented and their shortcomings are discussed. Based on the insights from the review, the desirable characteristics from the review, the desirable characteristics of advanced diagnostic met… more
Date: January 1, 1991
Creator: Kim, I.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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