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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

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

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

Use of a Water Boiler Reactor as a Production Test Facility

Description: The feasibility of the use of a water-boiler type reactor as a production test facility for making reactivity tests on various forms of uranium and uranium compounds was investigated. It is concluded that the reactor should be very useful for production testing of materials with the danger coefficient techniqus. A suggested production procedure is outlined. (auth)
Date: August 25, 1953
Creator: Remley, M. E.
Partner: UNT Libraries Government Documents Department

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.
Partner: UNT Libraries Government Documents Department

MODIFICATION OF THE EXPERIMENTAL BOILING WATER REACTOR (EBWR) FOR HIGHER- POWER OPERATION

Description: Supplement to ANL-5607. Alterations and additions made to the Experimental Boiling Water Reactor (EBWR) plant to permit operation at power levels up to I00 Mw(t) are described. Topics covered include over-all system modifications and additions, nuclear component modifications and additions, and reboiler plant component description. (M.C.G.)
Date: April 1, 1962
Creator: Matousek, J.F. comp.
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

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 test facility is proposed for construction at the Test Area North of the National Reactor Testing Station in Idaho. The site selection utilizes existing support facilities suited for performing nuclear safety tests requiring experiment assembly areas and post-test analytical examination of the irradiated nuclear components. (auth)
Date: April 24, 1963
Creator: Wilson, T.R.; Hauge, O.M. & Matheney, G.B.
Partner: UNT Libraries Government Documents Department