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Civilian Power Reactor Program. Part 3. Book 2. Status Report on Pressurized Water Reactors as of 1959

Description: The status of pressurized water reactors on a technical, economic, and operating experience basis is reported. Items covered include concept description, PWR objectives, general research and development prcgram, reactor data, reactor illustrations, operating experience, construction and operation schedules, and present limitations and problems. (W.D.M.)
Date: January 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Reactor Plant Leak Rate Test. Core 1, Seed 2. Test Results T- 641102. First Issue, June 14, 1961

Description: Tests were performed on the Shippingport PWR to determine the magnitude and location of coolant system leakages. The total leakage from pressurizer relief and reactor relief valves was 62.1 gal/hr. The total plant leakage was 19.3 gal/hr. (T.F.H.)
Date: October 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Borax Experiments

Description: An analysis of the self-limitation of power excursions by steam production in heterogeneous water-moderated reactors using MTR- type fuel elements seems to give excellent agreement with Borax data on both fuel plate temperature rise and total energy for excursions in which the reactor is initially at saturation temperature. A simple model for steam production is developed from thermodynamic and heat diffusion considerations. In those cases for which the reactor is substantially sub-cooled, it a… more
Date: January 1, 1955
Creator: Edlund, M.C. & Noderer, L.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of Remote Military Power Applications. Report No. 12. Evaluation and Selection of Applicable Reactor Concepts

Description: An evaluation of the reactor concepts under consideration for remote military power plants is presented. The concepts include water-cooled and - moderated reactors, both direct and indirect cycle. organic-cooled and -moderated reactors, heavy-water-cooled and -moderated reactors. gas-cooled reactors, sodium- cooled graphite-moderated reactors, fast reactors, and fluid-fuel reactors. The limitations and advantages, technological status, economics, and future potential of each reactor are reviewe… more
Date: January 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SPECTRAL SHIFT CONTROL REACTOR BASIC PHYSICS PROGRAM. Quarterly Technical Report No. 2, October-December 1960

Description: Basic physics parameters are being determined for lattices of slightly enriched fuel in moderators consisting of D/sub 2/O--H/sub 2/O mixtures of different concentrations. The principal effort was devoted to procurement and erection of equipment and materials needed for the critical experiments with D/ sub 2/O in the moderator, the exponential experiments, the hot exponential experiments, and the neutron age experiments. The erection of these facilities and the D/sub 2/O handling system was com… more
Date: October 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHARGING AND DISCHARGING OF DEMINERALIZER RESINS. CORE I, SEED 2. Test Results (T-612085). Section 1

Description: An investigation was conducted to flush the 1BD coolant purification system demineralizer of resin and to measurc the radiation level at pornts on the resin discharge line. It was found that the system demineralizer was satisfactorily flushed of resin. It was also found that the amount removed is measured by the amount required to recharge the demineralizer. (J.R.D.)
Date: January 10, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE OAK RIDGE RESEARCH REACTOR (ORR), THE LOW-INTENSITY TESTING REACTOR (LITR), AND THE OAK RIDGE GRAPHITE REACTOR (OGR) AS EXPERIMENT FACILITIES

Description: >Characteristics of the ORR, LITR, and OGR that experimenters have found to be important are listed. The results of a survey conducted among experimenters on the utility of the reactors for various types of experiments are discussed, and some changes which might be made to improve the utilization are listed. A brief outline, with references, of most of the experiments currently being performed is included. (auth)
Date: August 28, 1962
Creator: George, K.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey of Reactor Plant Container and Components After Shutdown "F" Survey. Core I, Seed 1. Test Results (T-612076). Section 4

Description: An investigation was conducted to obtain measurements of radiation levels inside the hemispherical heads of the 1-B heat exchanger. The radiation levels were measured at the handholes on two occasions with an interval of 640 hrs between them. A very large increase was noted and could be explained only by the possibility that the measurement survey points were not identical. (J.R.D.)
Date: October 17, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility and Conceptual Design for the Step Loss of Coolant Facility

Description: A summary of studies conducted on the pressurizedwater reactor loss-of- coolant accident is presented, and an experimental safety program is proposed. The various phenomena involved in the loss-of-coolant accident, related research and development programs, assumptions currently used to predict the various physical phenomena, and the general approach to be used in conducting the safety tests are discussed. In order to accomplish the loss-of-coolant experimental safety program, a dry containment… more
Date: April 24, 1963
Creator: Wilson, T. R.; Hauge, O. M. & Matheney, G. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Description and Startup of a Water Boiler Reactor

Description: A "water boiler" type reactor has been installed at the Livermore Research Laboratory. The reactor was designed and constructed by North American Aviation, Inc., for the Atomic Energy Commission as a neutron source for the California Research and Development Company. A detailed description of the reactor, critical experiment, and preliminary operating characteristics are given.
Date: June 1, 1954
Creator: Shortall, J. W.; Flora, J. W.; Graham, R. H. & Shelton, A. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Valve Operating System Performance Test. Core 1, Seed 2. Test Results T- 641114

Description: A test was run on the Shippingport Pressurized Water Reactor on June 15, 1960, to determine whether or not the pressure snd water flask volume of the valve operating system are sufficient to meet requirements under both normal and emergency conditions. The system was found to be satisfactory. A two-hour leak test indicated leakage. (D.L.C.)
Date: March 14, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part II. Economic Potential and Development Program. Heavy Water-Moderated Power Reactor

Description: The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel de… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modified Purification System Performance Test. Core I, Seed 2. Test Results (T-641124). Section 1

Description: An investigation was conducted to establish an operating procedure for flushing water through a purification system demineralizer which was out of service for an extended period, and to determine the demineralizer serviceability. (J.R.D.)
Date: September 14, 1960
Creator: Duquesne Light Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stress Analysis of the PM-2A Reactor Vessel

Description: The stress analysis performed on the PM-2A reactor vessel and cover is discussed. The maximum combined stress (51,000 psi) occurred in the studs after reaching steady-state conditions. A fatigue analysis indicated that this stress could be safely applied 2500 times, and since the studs do not approach 2500 cycles from initial stud tightening to steady-state conditions, they should not suffer any fatigue damage. (auth)
Date: May 14, 1962
Creator: Rowekamp, B. J.; McLaughlin, D. W.; Chittum, R. A. & Aitken, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PERIODIC WASTE DISPOSAL SYSTEM MATERIAL BALANCE TEST. CORE I, SEED 2. Section 2. Test Results T-641317

Description: ABS>A test was made on the Radioactive Waste Disposal (RWD) system to determine the acceptability of procedures used in containing, processing, and disposing the wastes received from the plant during a steady-state operation. The RWD system was found to be adequate and to have 60,000 gallons available at all times in the Surge and Decay tanks for safety injection. (D.L.C.)
Date: March 17, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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BOILING WATER REACTOR TECHNOLOGY STATUS OF THE ART REPORT. VOLUME II. WATER CHEMISTRY AND CORROSION

Description: Information concerning the corrosive effects of water in power reactor moderator-coolant systems is presented. The information is based on investigations reported in the unclassified literature believed to be fairly complete to 1959, but less complete since then. The material is presented in sections on water decomposition, water chemistry, materials corrosion, corrosion product deposits, and radioactivity. It is noted that the report is presented as a part of a continuing program in developmen… more
Date: February 1, 1963
Creator: Breden, C.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity Lifetime. Test Results DL-S-225(T-612118). Section I, First Performance

Description: The performance, reliability, and reactivity lifetime of the Shippingport PWR are determined under normal steady state conditions. These characteristics are studied over a period of 1011 EFPH, at a power level of about 60 Mw(e). Flux tilts that occurred during this time, as well as the means employed for their suppression, are described. (T.F.H.)
Date: October 24, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PHYSICS ANALYSIS OF PROPOSALS FOR EBWR CORE 2

Description: Two concepts were investigated as possibilities for the next loading of EBWR. One is a light water spiked plutonium recycle system; the second is a conventional uniformly loaded system with the option of different enrichments in two radial zones. It is concluded that the plutonium recycle scheme is not feasible in EBWR at 100 Mw, and recommendation for a two-enrichment loading for various burnups is made. (auth)
Date: April 1, 1961
Creator: Avery, R. & Kelber, C.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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River Soundings. Core I, Seed 2. Test Results

Description: Water depth in the intake channel to the coolant-water screenhouse and surrounding area in the Ohio River near the intake channel were measured. From these measurements, the amount of silt removed during a previous dredging was determined. (C.J.G.)
Date: July 18, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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