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REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT

Description: General research and development are reported on watercooled and sodium- cooled reactors. Studies are also reported on reactor safety and nuclear technology. (For preceding period, see Report ANL-6253.) (W.L.H.)
Date: November 1, 1960
Creator: Hilberry, N.
Partner: UNT Libraries Government Documents Department

ENGINEERING MATERIALS LIST. A Catalog of Drawings, Photographs, and Specifications Released by the United States Atomic Energy Commission. Supplement 1: SHIPPINGPORT PRESSURIZED WATER REACTOR

Description: Unclassified Engineering Materials List, TM-4100(lst Rev.), is a catalog of available U. S. Atomic Energy Commission unclassified engineering drawing materials on the peaceful applications of atomic energy. The engineering literature described in this publication includes drawing, specifications, photographs, bill of materials, cost analysis, design criteria, psrts lists, and supporting textual data. This consolidated list m- cludes all materials originally announced in TM-4100, January 1957, and TID-4100, Supplement 1, July 1957, and additional engineering data received and cataloged by TlSE after the original issuances. The entire publication, TID-4100 lst Revision Supplement 1, is devoted to the Shippingport Pressurized Water Reactor. (W.L.H.)
Date: May 1, 1958
Partner: UNT Libraries Government Documents Department

COMPARISON OF GASEOUS WASTE HANDLING SYSTEMS FOR PL-3

Description: Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in detail. Sufficient information is presented to enable one to analyze the methcds required to remove gaseous activity present in other size and type pressurized and boiIing water reactors. (auth)
Date: February 28, 1962
Creator: Noble, J.H. & Duke, E.E.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT CONCEPTUAL DESIGN STUDY OF CRBR QUICK- OPERATING PRESSURE VESSEL CLOSURE AND SELF-ENERGIZING SEAL TESTS. Final Report

Description: The work to determine the feasibility of using a quickoperating closure for the pressure vessel of the controlled Recirculation Boiling Reactor is described. An outline of the worb performed and the conclusions made is given. Datailed results of the self-energizing seal-evaluation tests are given. (W.D.M.)
Date: October 15, 1950
Creator: Michel, R.G.
Partner: UNT Libraries Government Documents Department

NAVAL REACTORS PHYSICS HANDBOOK. VOLUME I. SELECTED BASIC TECHNIQUES

Description: The purpose of this work is to present the most pertinent parts of the body of physics knowledge which has been built up in the course of the Naval and Shippingport (PWR) Reactor Programs, with the aim of providing a background of understanding for those interested in nuclear core design. Volume 1 of this handbook was planned to bring together topics in the basic theoretical and experimental material which are of especially wide interest, including those common to both thermal and intermediate neutron energy reactor types. The physics design of light water-moderated and -cooled reactors is covered in Volume 2 (classified), and that of intermediate neutron-energy power reactors in Volume 3. The emphasis in Volume 1 is thus on light water reactor systems, and as many recent advances in reactor physics of the Naval and Shippingport Reactor Programs as possible have been included.
Date: January 1, 1964
Creator: Radkowsky, A. ed.
Partner: UNT Libraries Government Documents Department

COST STUDY OF A 100-Mw(e) DIRECT-CYCLE BOILING WATER REACTOR PLANT

Description: A technical and economic evaluation is presented of a direct-cycle light- water boiling reactor designed for natural circulation and internal steam-water separation. The reference lOO-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. (W.D.M.)
Date: July 1, 1960
Creator: Bullinger, C.F. & Harrer, J.M.
Partner: UNT Libraries Government Documents Department

A MODEL OF BUBBLE GROWTH IN THE KEWB REACTOR

Description: Short-period transients (less than 15 msec) in the KEWB reactor are apparently controlled primarily by void production resulting from gas evolution in the core. A growth mechanism probably prevails during the short-period excursions which differs from that which occurs at longer periods. Experimental data were examined which showed that the energy transferred to the average bubble is an order of magnitude less than that required to cause bubble growth. It is believed, however, that the validity of the growth model can be established by refinements concerning energy availability deposited in the bubble area and by refinement of bubble-size distribution functions. (J.R.D.)
Date: January 1, 1959
Creator: Gamble, D.P.
Partner: UNT Libraries Government Documents Department

PERIODIC CALIBRATION OF TEMPERATURE SENSING ELEMENTS. CORE I, SEED 2. Test Results (T-641303-B)

Description: Tests were conducted to determine the direction and magnitude of any short- or long-term drift in core thermocouples, primary loop and pressurizer resistance thermometers, and resistance thermometers located in the secondary side of the boilers for Seed 2 at 2303 EFPH. It was found that drift in the core thermocouples is definite but random. Other findings are discussed and calibration data are presented graphically. (J.R.D.)
Date: April 14, 1961
Partner: UNT Libraries Government Documents Department

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
Partner: UNT Libraries Government Documents Department

A LOW COST PHYSICS AND ENGINEERING TRAINING REACTOR. Reactor Design and Feasibility Study

Description: The conceptual design of a low cost training reactor for the instruction of physicists and engineers is covered. It is conceived as an instructional tool for a course such as that given at the Oak Ridge School of Reactor Technology. The reactor is of a modified pool type, and is designed for a maximum power level of one Mw. This arrangement will accommodate engineering experiments, shielding experiments, and critical experiments as well as being useful as a neutron and gamma source. (auth)
Date: August 1, 1956
Creator: Brown, R.A.; Ackerman, M.W.; Batter, J.F. Jr.; Bell, D.W.; Dunlay, J.B.; Ellis, G.K. et al.
Partner: UNT Libraries Government Documents Department

REVIEW OF HRT FEEDWATER CONTROL SYSTEM

Description: The HRT feedwater control system was reviewed to determine adequacy of the present controls and to evaluate alternate systems as to feasibility and desirability. Results indicate that the present system is adequate for operation from one to five megawatts, but that trouble may be experienced below one megawatt and above five megawatts. Recommendations for improving operations of the present system are presented. Alternate systems of feedwater control are discussed. (auth)
Date: April 1, 1958
Creator: Moore, R.L.
Partner: UNT Libraries Government Documents Department