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Development of a reactor-coolant pump monitoring and diagnostic system. Project management report, October 1980-November 1981

Description: The objective of the project is to develop a reactor coolant pump monitoring and diagnostic system and collect sufficient data to permit analysts to determine why high outleakage and failures occur at Davis-Besse Nuclear Power Station, Unit 1. This report summarizes the work completed during the first period of performance, October 1, 1980, through November 30, 1981. During this period the members of the Project Team were selected and the detailed work management plans developed to take this project from conception, through detailed engineering, and finally to construction in the early part of 1982. The scope of work described includes system design, equipment selection for the computer-based data collection and diagnostic system, and computer software development to permit data collection and analysis.
Date: February 1, 1982
Creator: Sommerfield, G. A. & Morris, D. J.
Partner: UNT Libraries Government Documents Department

Assessment of non-backfittable concepts to improve PWR uranium utilization

Description: Seven non-backfittable improvements to light water reactors were assessed for Batelle/Pacific Northwest Laboratories in support of the Department of Energy's program on Advanced Reactor Studies. The objective was to provide industrial perspective as to which concepts have the best potential for development to improve fuel utilization. The concepts were rated against the assessment criteria while considering the key questions identified for each concept, and recommendations were made for further action on unresolved key questions. The concepts were subjectively ranked against each other in terms of relative investment potential. The ranking considered all criteria but, for example, weighted fuel utilization savings more heavily than development costs. Finally, conclusions and recommendations for future action were determined. The reference design for this study was the NASAP Composite Improved PWR.
Date: December 1, 1980
Creator: LaBelle, D.W.; Sankovich, M.F.; Spetz, S.W. & Uotinen, V.O
Partner: UNT Libraries Government Documents Department

400-MWe Consolidated Nuclear Steam System (CNSS). 1200-MWt Phase 2A interim studies. [PWR]

Description: The Phase 2A interim studies of the Consolidated Nuclear Steam System (CNSS) consisted of a number of separate task studies addressing the design concepts developed during the Phase 1 study reported in BAW--1445. The purpose of the interim studies was to better establish overall concept feasibility from both a hardware and economic standpoint, to make modification and additions to the design where appropriate, and to understand and reduce the technical risks in critical areas of the design. The work on these task studies included input from Barberton, Mt. Vernon, and the Alliance Research Center as well as United Engineers and Constructors (UE and C). The UE and C work was carried out under a separate DOE contract.
Date: September 1, 1978
Partner: UNT Libraries Government Documents Department

Refueling outage availability study. Phase 1 final report

Description: Babcock and Wilcox entered into a contract with the Department of Energy (formerly the Energy Research and Development Administration) for the performance of a refueling outage availability study with the cooperation of Duke Power Company and Arkansas Power and Light Company. The objective was to improve plant availability through reduction of refueling outage time. The conclusions of the study were drawn from data gathered during the 1976 Oconee 3 and 1977 Arkansas Unit One refueling outages. The onsite effort was one of observation and data recording, which included time-lapsed photography and video tape. The collected data were then evaluated and analyzed for potential improvements and to identify in detail where resources were consumed. The overall result was a listing of (1) specific recommendations for implementing improvements in the facilities, equipment, tools, procedures, and techniques for the participating utilities; (2) generic recommendations of immediate benefit to other applicable utilities; and (3) recommendations for further work in the succeeding phases of the DOE program. The results indicate that, by incorporating the recommendations and taking credit for the time savings, an ideal refueling outage length of 21 to 22 days for the nuclear steam system (NSS) could be realized. Additional benefits would be a reduction in man-Rem exposure and manpower requirements.
Date: November 1, 1977
Creator: Thomasson, F.R.
Partner: UNT Libraries Government Documents Department

Oconee 1, cycle 5 design report

Description: The Oconee 1, cycle 5 fuel cycle was designed to irradiate five fuel assemblies to a burnup of approximately 40,000 MWd/mtU. The fuel cycle design was performed using standard Babcock and Wilcox calculational techniques for nuclear fuel cycles. All applicable design criteria were satisfied. Valuable experimental data on the performance characteristics of high-burnup fuel assemblies will be obtained from these assemblies in subsequent post-irradiation examinations.
Date: May 1, 1979
Creator: Coleman, T.A. (ed.)
Partner: UNT Libraries Government Documents Department

Nondestructive examination of Oconee 1 fuel assemblies after three cycles of irradiation

Description: The Babcock and Wilcox Company (B and W) in conjunction with Duke Power Company is participating in a Department of Energy sponsored research and development program to qualify current design pressurized water reactor (PWR) fuel assemblies for extended burnup (>40,000 MWd/mtU). The information obtained from this program will provide a basis for future design improvements in PWR fuel assemblies culminating in an extended burnup assembly having a nominal operating limit of approximately 50,000 MWd/mtU. An extension of the current assembly design to higher burnups will result in the following benefits: (1) lower uranium ore requirements, (2) greater fuel cycle efficiency, (3) reduction in spent fuel storage requirements, and (4) increased flexibility in tailoring fuel batch sizes to better accommodate the varying energy requirements of the utilities.
Date: September 1, 1979
Creator: Pyecha, T.D.; Davis, H.H.; Mayer, J.T.; Guthrie, B.A. III & Larson, J.G.
Partner: UNT Libraries Government Documents Department

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) thorium blankets, and (3) ThO/sub 2/ rods placed in available guide tubes. A conceptual core design incorporating these changes was then developed, and the fuel utilization of this modified design was compared with that of the reference case.
Date: June 1, 1980
Creator: Jones, H.M.; Schwenk, G.A.; Toops, E.C. & Yotinen, V.O.
Partner: UNT Libraries Government Documents Department

Qualification of the B and W Mark B fuel assembly for high burnup. First semi-annual progress report, July-December 1978

Description: Five Babcock and Wilcox standard Mark B (15 x 15) fuel assemblies are being irradiated in Duke Power Company's Oconee Unit 1 reactor under a research and development program sponsored by the U.S. Department of Energy. Valuable experimental data on fuel performance characteristics at burnups of > 40,000 MWd/mtU will be obtained from these assemblies. This information, at a duty approximately 20% greater than that achieved by typical discharged assemblies, will be used to qualify standard Mark B fuel assemblies for extended burnups. Efforts during this period included fuel cycle design and reload licensing of Oconee 1 for cycle 5, in which the assemblies are being irradiated, and nondestructive examination of the assemblies during the refueling outage between cycles 4 and 5. The Oconee 1 cycle 5 startup tests proceeded in a routine manner, and the reactor has operated with a 92% capacity factor since completion of power escalation testing on November 10, 1978. Irradiation of the fuel assemblies is currently in progress.
Date: August 1, 1979
Creator: Coleman, T.A.; Coppola, E.J.; Doss, P.L.; Uotinen, V.O. & Davis, H.H.
Partner: UNT Libraries Government Documents Department

In-air vibration analysis of Three Mile Island Unit-2 once-through steam generator tubes. Volume 1

Description: Resonant frequencies were determined for 100 randomly selected tubes and tubes selected for instrumentation during power operation. The average fundamental resonant frequency of the tubes tested was approximately 65 Hz. No spatial distribution of resonant frequency associated with the OTSG was discerned. Mode shapes were determined for five tube spans bounded by the fifteenth support plate and upper tubesheet and one tube span between the ninth and tenth support plates. The boundary conditions associated with the mode shapes varied from simple support to clamped at both ends. The in-air test results are useful for interpreting test data acquired from the permanently installed instrumentation during power operation at Three Mile Island Unit 2.
Date: October 1, 1982
Creator: Simonis, J.C.
Partner: UNT Libraries Government Documents Department

Li/sub 2/O microsphere fabrication. Monthly letter progress report No. 1 for the period ending May 31, 1977

Description: The purpose of this task is to establish process parameters for the fabrication of lithium oxide (Li/sub 2/O) microspheres having properties which as closely as possible approximate those required for the design characteristics of the University of Wisconsin design for a TOKAMAK-type fusion reactor utilizing the moving bed of Li/sub 2/O microspheres as both reactor coolant and tritium breeder.
Date: June 1, 1977
Creator: Schluderberg, D C
Partner: UNT Libraries Government Documents Department

Gaseous waste treatment system

Description: No Description Available.
Date: May 1, 1973
Creator: Heck, K.C. & Marrero, T.R.
Partner: UNT Libraries Government Documents Department