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in subjects: "21 Specific Nuclear Reactors And Associated Plants"  
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Common-Cause Failure Analysis for Reactor Protection System Reliability Studies

Description: Analyses were performed of the safety-related performance of the reactor protection system (RPS) at U.S. Westinghouse and General Electric commercial reactors during the period 1984 through 1995. RPS operational data from these reactors were collected from the Nuclear Plant Reliability Data System (NPRDS) and Licensee Event Reports (LER). The common-cause failure (CCF) modeling in the fault trees developed for these studies and the analysis and use of common-cause failure data were sophisticate… more
Date: August 1, 1999
Creator: Gentillon, C.; Rasmuson, D.; Eide, S. & Wierman, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Preliminary Risk Assessment Associated with IGSCC of BWR Vessel Internals

Description: BWR core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission (NRC) has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory (INEEL) to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel… more
Date: August 1, 1999
Creator: Ware, Arthur; Morton, Keith; Nitzel, Michael; Chokshi, Nilesh & Chang, Tsun-Yung
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A Program for Risk Assessment Associated with IGSCC of BWR Vessel Internals

Description: A program is being carried out for the US Nuclear Regulatory Commission (NRC) by the Idaho National Engineering and Environmental Laboratory (INEEL), to conduct an independent risk assessment of the consequences of failures initiated by intergranular stress corrosion cracking (IGSCC) of the reactor vessel internals of boiling water reactor (BWR) plants. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel int… more
Date: August 1, 1999
Creator: Ware, Arthur G.; Morton, D. Keith; Page, Joel D.; Nitzel, Michael E.; Eide, Steven A. & Chang, T. -Y.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Westinghouse Reactor Protection System Unavailability, 1984-1995

Description: An analysis was performed of the safety-related performance of the reactor protection system (RPS) at U.S. Westinghouse commercial reactors during the period 1984 through 1995. RPS operational data were collected from the Nuclear Plant Reliability Data System and Licensee Event Reports. A risk-based analysis was performed on the data to estimate the observed unavailability of the RPS, based on a fault tree model of the system. Results were compared with existing unavailability estimates from In… more
Date: August 1, 1999
Creator: Gentillon, C. D.; Marksberry, D.; Rasmuson, D.; Calley, M. B.; Eide, S. A. & Wierman, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Decay heat removal by natural convection - the RVACS system.

Description: In conclusion, this work shows that for sodium coolant the reactor vessel auxiliary cooling system (RVACS) is an effective passive heat removal system if the reactor power does not exceed about 1600 MW(th). Its effectiveness is limited by the effective radiative heat transfer coefficient in the inner gap. In a lead cooled system, economic considerations may impose a lower limit.
Date: August 17, 1999
Creator: Tzanos, C. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

General Electric Reactor Protection System Unavailability, 1984-1995

Description: An analysis was performed of the safety-related performance of the reactor protection system (RPS) at U.S. General Electric commercial reactors during the period 1984 through 1995. RPS operational data were collected from the Nuclear Plant Reliability Data System and Licensee Event Reports. A risk-based analysis was performed on the data to estimate the observed unavailability of the RPS, based on a fault tree model of the system. Results were compared with existing unavailability estimates fro… more
Date: August 1, 1999
Creator: Gentillon, C. D.; Rasmuson, D.; Hamzehee, H.; Calley, M. B.; Eide, S. A. & Wierman, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Elevated-Temperature Mechanical Properties of an Advanced Type 316 Stainless Steel

Description: Type 316FR stainless steel is a candidate material for the Japanese Demonstration Fast Breeder Reactor Plant to be built in Japan early in the next century. Like type 316L(N), it is a low-carbon grade of stainless steel with a more closely specified nitrogen content and chemistry optimized to enhance elevated-temperature performance. Early in 1994, under sponsorship of The Japan Atomic Power Company, work was initiated at Oak Ridge National Laboratory (ORNL) aimed at obtaining an elevated-tempe… more
Date: August 1, 1999
Creator: Brinkman, C.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Validation Work to Support the Idaho National Engineering and Environmental Laboratory Calculational Burnup Methodology Using Shippingport Light Water Breeder Reactor (LWBR) Spent Fuel Assay Data

Description: Six uranium isotopes and fourteen fission product isotopes were calculated on a mass basis at end-of-life (EOL) conditions for three fuel rods from different Light Water Breeder Reactor (LWBR) measurements. The three fuel rods evaluated here were taken from an LWBR seed module, a standard blanket module, and a reflector (Type IV) module. The calculated results were derived using a depletion methodology previously employed to evaluate many of the radionuclide inventories for spent nuclear fuels … more
Date: August 1, 1999
Creator: Sterbentz, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Insights About Emergency Diesel Generator Failures from the USNRC's Common Cause Failure Database

Description: The US Nuclear Regulatory Commission has sponsored development of a database of common cause failure events for use in commercial nuclear power plant risk and reliability analyses. This paper presents a summary of the results from analysis of the emergency diesel generator data from the database. The presentation is limited to the overall insights, the design and manufacturing cause and the instrumentation and control sub-system.
Date: August 1, 1999
Creator: Mosleh, A.; Rasmuson, D.; Marshall, F. & Wierman, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Signal trend identification with fuzzy methods.

Description: A fuzzy-logic-based methodology for on-line signal trend identification is introduced. Although signal trend identification is complicated by the presence of noise, fuzzy logic can help capture important features of on-line signals and classify incoming power plant signals into increasing, decreasing and steady-state trend categories. In order to verify the methodology, a code named PROTREN is developed and tested using plant data. The results indicate that the code is capable of detecting tran… more
Date: August 19, 1999
Creator: Reifman, J.; Tsoukalas, L. H.; Wang, X. & Wei, T. Y. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermionic Converter Temperature Controller

Description: A method and apparatus for controlling the temperature of a thermionic reactor over a wide range of operating power, including a thermionic reactor having a plurality of integral cesium reservoirs, a honeycomb material disposed about the reactor which has a plurality of separated cavities, a solid sheath disposed about the honeycomb material and having an opening therein communicating with the honeycomb material and cavities thereof, and a shell disposed about the sheath for creating a coolant … more
Date: August 23, 1999
Creator: Shaner,B. J.; Wolf, Joseph H. & Johnson, Robert G. R.
Item Type: Refine your search to only Patent
Partner: UNT Libraries Government Documents Department
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