Search Results

Advanced search parameters have been applied.
open access

Fuel performance annual report for 1989

Description: This annual report, the twelfth in a series, provides a brief description of fuel performance during 1989 in commercial nuclear power plants and an indication of trends. Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance are provided. References to more detailed information and related US Nuclear Regulatory Commission evaluations are included.
Date: June 1, 1992
Creator: Bailey, W.J.; Berting, F.M. (Pacific Northwest Lab., Richland, WA (United States)) & Wu, S. (Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology)
Partner: UNT Libraries Government Documents Department
open access

Configuration Management Program Plan

Description: Westinghouse Savannah River Company (WSRC) has established a configuration management (CM) plan to execute the SRS CM Policy and the requirements of the DOE Order 4700.1. The Reactor Restart Division (RRD) has developed its CM Plan under the SRS CM Program and is implementing it via the RRD CM Program Plan and the Integrated Action Plan. The purpose of the RRD CM program is to improve those processes which are essential to the safe and efficient operation of SRS production reactors. This docume… more
Date: September 25, 1991
Partner: UNT Libraries Government Documents Department
open access

Nuclear plant-aging research on reactor protection systems

Description: This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show th… more
Date: January 1, 1988
Creator: Meyer, L.C.
Partner: UNT Libraries Government Documents Department
open access

Use of ICRH for startup and initial heating of the TMX-U central cell

Description: Ion cyclotron resonance heating (ICRH) was evaluated and it was found to be satisfactory for use in establishing the conditions necessary to form a thermal barrier in TMX-upgrade (TMX-U). We discuss the constraints that must be satisfied in order to maintain a plasma, and outline a complete startup scenario that ends with the plasma at design parameters. The detailed discussions in this report concentrate on those parts of startup where ICRH is necessary. The ability of ICRH to couple power int… more
Date: May 1, 1982
Creator: Molvik, A.W. & Falabella, S.
Partner: UNT Libraries Government Documents Department
open access

Natural convection phenomena in a nuclear power plant during a postulated TMLB' accident

Description: After the TMI (Three Mile Island) accident, there has been significant interest in analyzing and understanding the phenomena that may occur in a PWR (Pressurized Water Reactor) accident which may lead to partial or total core meltdown and degradation. Natural convection is one of the important phenomena. In the present paper the results of two numerical simulations of (1) four-loop PWR and (2) three-loop PWR are presented. The simulations were performed with the COMMIX(2) computer code. Our ana… more
Date: January 1, 1987
Creator: Domanus, H. M.; Schmitt, R. C.; Sha, W. T.; Shah, V. L. & Han, J. T.
Partner: UNT Libraries Government Documents Department
open access

Summary data for U. S. commercial nuclear power plants in the United States

Description: A compilation of data is presented for all United States commercial nuclear power plants for which a construction permit application was made through the Nuclear Regulatory Commission. The data are compiled in four separate tables with cross-referencing indexes: Table 1--General Data; Table 2--Reactor Data; Table 3--Site Data, and Table 4--Circulating-Water System Data. The power plants are listed in numerical order by docket number in all four tables.
Date: March 20, 1978
Creator: Heddleson, F.A.
Partner: UNT Libraries Government Documents Department
open access

Measurement of stochastic flow-induced power fluctuations at LOFT

Description: Investigation of power fluctuations at LOFT began after peak to peak power fluctuations of 1.5% of full power were observed prior to Loss of Coolant Experiment L2-3. The power fluctuations are caused by fluctuations in primary coolant flow. The fluctuations in coolant flow result in fluctuations in moderator temperature, which through the moderator coefficient of reactivity, cause the power fluctuations. This conclusion is supported experimentally by the high coherence between power and flow, a… more
Date: January 1, 1980
Creator: Cannon, J.W. & Clemo, T.M.
Partner: UNT Libraries Government Documents Department
open access

Operating and test experience of EBR-II

Description: EBR-2 has operated for 27 years, the longest for any Liquid Metal Reactor (LMR) power plant. During that time, much has been learned about successful LMR operation and design. The basic lesson is that conversatism in design can pay significant dividends in operating reliability. Furthermore, such conservatism need not mean high cost. The EBR-2 system emphasizes simplicity, minimizing the number of valves in the heat transport system, for example, and simplifying the primary heat-transport-syste… more
Date: January 1, 1991
Creator: Sackett, J. I.
Partner: UNT Libraries Government Documents Department
open access

Time series analysis of reactor thermocouple data. [LMFBR]

Description: Time-series analysis techniques are applied to nuclear reactor thermocouple data to investigate coolant temperatures measured within the fueled test assembly. The coolant temperature distribution within a fuel assembly affects the length of time a fuel assembly may be operated in a power reactor and, therefore, is an important economic consideration in the design of reactor fuel systems. Frequency-domain signal conditioning techniques were used to reveal the smoothly varying thermocouple signal… more
Date: April 10, 1980
Creator: Devary, J.L.
Partner: UNT Libraries Government Documents Department
open access

Cycle 7 outage experience. [Fast Flux Test Facility (FFTF)]

Description: The scheduled 58-day refueling outage in preparation for the seventh operating cycle of the Fast Flux Test Facility (FFTF) was successfully completed three days ahead of schedule. The planning and execution of the outage was greatly aided by Project/2 automated scheduling capabilities. For example, the use of ''maintenance windows'' and resource loading capabilities was particularly effective. The value of the planning process was demonstrated by the smooth transition into the outage phase afte… more
Date: March 1, 1986
Creator: Gadeken, A.D.
Partner: UNT Libraries Government Documents Department
open access

High Flux Isotope Reactor. Quarterly report, October, November, and December 1979

Description: Routine reactor operation with four end-of-cycle shutdowns and one scheduled midcycle shutdown resulted in an on-stream time of 93.6% for the quarter. This gave the HFIR an on-stream time for the year of 91.3%. The outer control plates were replaced, and the annual core components inspection was made.
Date: August 1, 1980
Creator: Corbett, B.L. & Poteet, K.H.
Partner: UNT Libraries Government Documents Department
open access

Comparison of predicted and measured fission product behavior in the Fort St. Vrain HTGR during the first three cycles of operation

Description: Fission product release from the reactor core has been predicted by the reference design methods and compared with reactor surveillance measurements and with the results of postirradiation examination (PIE) of spent FSV fuel elements. Overall, the predictive methods have been shown to be conservative: the predicted fission gas release at the end of Cycle 3 is about five times higher than observed. The dominant source of fission gas release is as-manufactured, heavy-metal contamination; in-servi… more
Date: October 1, 1985
Creator: Hanson, D. L.; Jovanovic, V. & Burnette, R. D.
Partner: UNT Libraries Government Documents Department
open access

Fuel Utilization Improvement in PWRs Using the Denatured /sup 233/U-Th Cycle

Description: A number of changes in PWR core design and/or operating strategy were evaluated to assess the fuel utilization improvement achievable by their implementation in a PWR using thorium-based fuel and operating in a recycle mode. The reference PWR for this study was identical to the B and W Standard Plant except that the fuel pellets were of denatured (/sup 233/U//sup 238/U-Th)O/sub 2/. An initial scoping study identified the three most promising improvement concepts as (1) a very tight lattice, (2)… more
Date: June 1, 1980
Creator: Jones, H. M.; Schwenk, G. A.; Toops, E. C. & Uotinen, V. O.
Partner: UNT Libraries Government Documents Department
open access

High flux isotope reactor quarterly report, July, August, and September of 1981

Description: Routine reactor operation with four end-of-cycle shutdowns and two unscheduled shutdowns resulted in an on-stream time of 91.3% for the quarter. The outer control plates and the inner control cylinder were changed and a semi-annual core component inspection was made.
Date: April 1, 1982
Creator: Corbett, B. L. & Poteet, K. H.
Partner: UNT Libraries Government Documents Department
open access

Recent operational history of the new Sandia Pulsed Reactor III (SPR III)

Description: The Sandia Pulsed Reactor III (SPR III) is a fast-pulse research reactor which was designed and built at Sandia Laboratories and achieved criticality in August 1975. The reactor is now characterized and is in an operational configuration. The core consists of 18 fuel plates (258 kg fuel mass) of fully enriched uranium alloyed with 10 wt.% molybdenum. It is arranged in an annular configuration with an inside diameter of 17.78 cm, an outside diameter of 29.72 cm, and a height of 35.9 cm. The reac… more
Date: January 1, 1977
Creator: Schmidt, T. R.; Estes, B. F. & Reuscher, J. A.
Partner: UNT Libraries Government Documents Department
open access

Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Final report

Description: The present study was designed to identify the impact of maintenance and testing (M and T) upon the safety of LWR power plants. The study involved data extraction from various sources reporting safety-related and operation-related nuclear power plant experience. Primary sources reviewed, including Licensee Event Reports (LER's) submitted to the NRC, revealed that only ten percent of events reported could be identified as M and T problems. The collected data were collated in a manner that w… more
Date: April 1, 1980
Creator: Husseiny, A. A.; Sabri, Z. A. & Turnage, J. J.
Partner: UNT Libraries Government Documents Department
open access

The use of NPAR (Nuclear Plant Aging Research) results in plant inspection activities

Description: The US NRC's Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. Equipment and systems which have a propensity for age related degradation are identified, and methods for detecting and mitigating aging effects have been evaluated. As plants age, it becomes increasingly important that NRC inspectors be cognizant of plant aging phenomena. This paper describ… more
Date: January 1, 1989
Creator: Gunther, W. & Taylor, J.
Partner: UNT Libraries Government Documents Department
open access

Aging assessment of auxiliary feedwater systems

Description: A study of Pressurized Water Reactor Auxiliary Feedwater (AFW) Systems has been conducted by Oak Ridge National Laboratory (ORNL) under the auspices of the Nuclear Regulatory Commission's Nuclear Plant Aging Research Program. The study has reviewed historical failure experience and current monitoring practices for the AFW System. This paper provides an overview of the study approach and results. 7 figs.
Date: January 1, 1989
Creator: Casada, D.A. (Oak Ridge National Lab., TN (USA))
Partner: UNT Libraries Government Documents Department
open access

Bulk shielding facility quarterly report, January, February, and March 1981

Description: The BSR operated at an average power level of 1954 kW for 59.3% of the time during January, February, and March. Water-quality control in both the reactor primary and secondary cooling systems was satisfactory. The PCA was used in training programs and was operated on nine occasions. Nuclear engineering students from the University of Tennessee actively participated in training laboratories. The PCA was also operated on thirteen occasions for the Pressure Vessel Simulator Benchmark experiment.
Date: January 1, 1982
Creator: Hurt, S. S.; Lance, E. D. & Thomas, J. R.
Partner: UNT Libraries Government Documents Department
open access

Licensee Event Report (LER) compilation for month of February 1984. Vol. 3, No. 2

Description: This monthly report contains LER operational information that was processed into the LER data file of the Nuclear Safety Information Center (NSIC) during this period. The LER summaries are arranged alphabetically by facility name and then chronologically by event date for each facility. Component, system, keyword, and component vendor indexes follow the summaries.
Date: March 1, 1984
Partner: UNT Libraries Government Documents Department
open access

Operational safety system reliability. Final report, November 15, 1975--November 14, 1976

Description: A computerized system is described which is to be used in conjunction with operational data (observed failure rates) of nuclear power plant components. The codes convert the system description to its Boolean equivalent and obtain the system reliability vs. time. Additional codes provide a measure of the uncertainty in this calculated system reliability.
Date: December 1, 1977
Creator: Hockenbury, R. W.
Partner: UNT Libraries Government Documents Department
open access

Hanford production reactor heat releases 1951--1971

Description: The purpose of this report is to document and detail the thermal releases from the Hanford nuclear production reactors during the period 1951 through 1971, and to put these releases in historical perspective with respect to changing Columbia River flows and temperatures. This information can also be used as a foundation for further ecological evaluations. When examining Hanford production reactor thermal releases to the Columbia River all related factors affecting the releases and the character… more
Date: April 1, 1992
Creator: Kannberg, L.D.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen