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PROCEEDINGS OF THE US/UK MEETING ON THE COMPATIBILITY PROBLEMS OF GAS- COOLED REACTORS HELD AT OAK RIDGE NATIONAL LABORATORY, FEBRUARY 24-26, 1960

Description: Forty papers presented at the US/UK Meeting on the Compatibility Problems of Gas Cooled Reactors are given. Thirty-two of the papers are covered by separate abstracts. Eight papers were previously abstracted for NSA. (M.C.G.)
Date: March 1, 1961
Partner: UNT Libraries Government Documents Department

CORE LEVITATION IN THE EGCR IN CASE OF MAIN COOLANT PIPE FAILURE

Description: Results of an analysis to determine the extent of displacement of the EGCR core due to blowdown in case of several postulated hot main gas coolant pipe failures are summarized. Results show that the core will be damaged for ary hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing prior to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect. (auth)
Date: August 4, 1959
Creator: Fontana, M.H.
Partner: UNT Libraries Government Documents Department

NUMERICAL RESULTS FOR EGCR MODERATOR-ELEMENT STRESS PROBLEMS

Description: A detailed presentation is made of the thermal stresses calculated for the moderater elements in the Experimental Gas-Cooled Reactor. These results are discussed and some conclusions are presented. This report complements a previous report, BMI-1503, which defines the problems and discusses the methods of solution. (auth)
Date: July 1, 1961
Creator: Hulbert, L.E. & Redmond, R.F.
Partner: UNT Libraries Government Documents Department

EXPERIMENTAL BERYLLIUM OXIDE REACTOR PROGRAM. Quarterly Progress Report for the Period, January 1 through March 31, 1962

Description: Progress made in the development of the Experimental Beryllium Oxide Reactor (EBOR) is reported. The objective of the EBOR program is to develop a gas-cooled, beryllium oxide-moderated reactor which can be used in conjunction with a closed-cycle gas turbine or a steam cycle for a small land-based or a maritime power plant. Progress is reported on reactor development, reactor physics, and materials development. (N.W.R.)
Date: April 25, 1962
Partner: UNT Libraries Government Documents Department

Report of the Objectives and Plans for the AEC's Civilian Power Gas Cooled Reactor Program

Description: Progress in the U. S. civilian power gas-cooled reactor program is discussed. Gas reactors having technical features of high conversion ratio, high temperature, high fuel burnup, and capability of construction in large sizes make them very attractive as potential producers of economic power in the very near term. The operation of Peach Bottom-HTGR and EGCR in late 1964 and 1965, respectively, will contribute to the successful exploitation of thermal gas- cooled reactors. Since the graphite fuel concept promises very low fuel cycle costs along with reactor coolant conditions that can exceed current practice, it was concluded that the concept provides a long term potential that promises some very exciting possibilities. (auth)
Date: June 1, 1963
Creator: Pahler, R. E.
Partner: UNT Libraries Government Documents Department

HEAT TRANSFER EXPERIMENTS OF THE TITLE II FUEL ASSEMBLY FOR THE EXPERIMENTAL GAS COOLED REACTOR. SECTION IV OF THE FUEL ASSEMBLY HEAT TRANSFER AND CHANNEL PRESSURE DROP EXPERIMENT OF THE EGCR RESEARCH AND DEVELOPMENT PROGRAM. Report RD-0010

Description: ABS>Experimental heat transfer data and analysis are reported for the Title II fuel assembly design modifications and refinements. Three distinct mid- length spacer designs are described. All tests are conducted with a 3,000-in. M fuel assembly sleeve and with the six outer tubes (of the seven tube cluster) located on a 2.000-in. BC. The dath are presented as heat transfer correlations and as comparisons of the heat transfer test results of one design with the results obtained from the other two and also the test results of the Title I fuel assembly design spacers. (auth)
Date: October 3, 1960
Creator: McDonald, T.J. & Higgins, R.M.
Partner: UNT Libraries Government Documents Department

DESIGN AND ANALYSIS: CORE STRUCTURE AND BOTTOM PLATE

Description: plate and to calculate its critical dimensions. Calculations were made which show that the plate and positioning keys meet the design requirements. Work sheets pertaining to the evaluation are included along with references to drawings. (J.R.D.)
Date: April 21, 1960
Creator: Goulden, P.V.
Partner: UNT Libraries Government Documents Department

GRAPHITE PROBLEMS IN AIR-COOLED REACTORS

Description: The problems of oxidation, radiation induced dimensional expansions, and accumulation of stored energy affect long term use of graphite in air-cooled reactors. Results show that frequent low temperature annealing eliminates these problems and may extend the lifetime of the graphite indefinitely. (N.W.R.)
Date: January 1, 1962
Creator: Schweitzer, D.G.
Partner: UNT Libraries Government Documents Department

LOSS-OF-PRESSURE ACCIDENT--HOT LEG PIPING FAILURE--QUICK-OPENING VALVES IN REACTOR BYPASS LINES

Description: Activities in a study to determine the differential pressure across the EGCR core following a pipe rupture in of quick-opening valves in bypass lines around the reactor are evaluated, and recommendations concerning these valves and other components are included. (J.R.D.)
Date: June 17, 1960
Creator: Landoni, J. A.
Partner: UNT Libraries Government Documents Department

COMPARISON OF GASES FOR USE AS THE COOLANT IN A GAS-COOLED REACTOR

Description: The expression STAM(Pr) /sup 2/3//(M Cp)/sup 3/! which is often used to compare the merits of various gas coolants is derived and the errors involved in using this term are discussed. An example using CO/sub 2/ and He is shown to illustrate the difference between the true pumping power required and that predicted by the above expression. (auth)
Date: April 28, 1958
Creator: Samuels, G.
Partner: UNT Libraries Government Documents Department

ANALOG COMPUTER STUDY OF THE OPERATION OF THE GAS-COOLED LOOP ON THE OAK RIDGE RESEARCH REACTOR

Description: An annlog computer study of the ORR gas-cooled loop was made. The effects on fuel and gas temperatures of changing gas (nitrogen) flow rates, turning the heater on and off, and inserting or removing the fuel were determined. It was found that the temperature of the sample, if fuel, could be raised more rapidly than it could be reduced, and that the temperature could be reduced faster with high rates of flow. All of the equations used in building up the computer are given, and some of them are derived. (auth)
Date: July 1, 1958
Creator: Green, F.P.; Neill, F.H.; Short, B.E. & Winton, M.L.
Partner: UNT Libraries Government Documents Department

Preliminary Evaluation of Chlorine for Use as a Gas Cooled Reactor Safeguard

Description: An evaluation of chlorine in a high-temperature gascooled graphite- moderated reactor as a safeguard to control u runawav oxidation reaction was made. Experiments were performed which demonstrated the ability of a small amount of chlorine in an air stream to reduce the oxidation rate of graphite. Chlorine appeared to inhibit graphite oxidation by blocking active sites on the surface. On the basis of this mechanism, a rate law was derived which was consistent with observed behavior. (C.J.G.)
Date: March 1, 1960
Creator: Dahl, R. E.
Partner: UNT Libraries Government Documents Department

LOSS-OF-PRESSURE ACCIDENT. HOT LEG PIPING FAILURE

Description: Results are presented of a study to determine if a circumferential rupture in the EGCR hot-leg piping just downstream of the block valve, accompanied by complete lateral displacement of the pipe ends such that the exhaust flows do not oppose each other, will result in excessive pressure differentials across the reactor core. Conclusions and recommendations are included. (J.R.D.)
Date: January 11, 1962
Creator: De Agazio, A.W.
Partner: UNT Libraries Government Documents Department

GAS-COOLED REACTORS BIBLIOGRAPHY

Description: A compilation of 517 references to the unclassified literature to May 1959 on gas-cooled reactors is presented. It includes articles, reports, books, and patents, Reactors cooled by air are included, as well as all types of reactors by function--power reactors, research reactors, design studies, and prototypes. (W.D.M.)
Date: September 1, 1959
Creator: Richardson, W.H. & Strachwitz, F. comps.
Partner: UNT Libraries Government Documents Department

Test of Heater and Cooler Concepts for GCR-ORR Loop, Design 4

Description: High heat flux electrical cartridge heaters were tested with direct air cooling under simulated ORR Loop conditions. The cartridges and the heater design were found to be satisfactory. A gas cooler of concentric pipe design utilizing air, water, and air-water mixtures as the coolant was also evaluated and found to be satisfactory. Heat transfer calculations are compared with the experimental data and found to correlate within 10%. (auth)
Date: July 13, 1959
Creator: Kelley, W. H., Jr. & Storto, E.
Partner: UNT Libraries Government Documents Department

PL Final Design Report. Supplement

Description: The design of the Army Reactor PL refueling equipment is described. Details of refueling procedures are also given along with a definitive hardware design for the radioactive gas handling equipment which is described in report IDO19030. (J.R.D.)
Date: January 1, 1961
Partner: UNT Libraries Government Documents Department

GCRE CRITICAL-ASSEMBLY STUDIES

Description: Critical-assembly studies were made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiment-1 (GCRE-l). Measurements of critical mass, flux and power distributions, and shutdown worth of the GCRE-1 mock-up safety and control blades were obtained. The critical assembly consists of aluminum tubes containing four concentric stainless steel cylinders wrapped wtth highly enriched uranium foil. These tubes are supported at each end by grid plates aiid arranged to approximate a right circular cylinder. The entire core structure is supported within a tank which can be filled remotely with moderator water. A void beneath the core structure and the air above it represent the gas plenums of the GCRE-1 reactor. Critical mass and flux power distributions were determined for several cases of four basic cores. The thermal utilization, measured in two core configurations, was 0.780 for the reactor wtthout burnable poison or a lead reflector. The temperature coefficient of reactivity, measured in two cores, was positive at room temperature but negative in the proposed operatingtemperature range. The total reactivity effect in going from 20 to 80 deg C was a positive 0.22% DELTA k/k. The worth of control and safety-shutdown blades of several compositions and sizes in various locations was determined for a number of core configurations; blades having a sandwich construction of cadmium, tungsten, and indium had the greatest shutdown worth. To date these studies have resulted in a 61-element core (critical with 54 elements) with a 4-in. lead reflector which has 2.5% DELTA k/k excess reactivity for startup and for override of poison and burnup. A mock-up blade configuration has been determined which will control the excess reactivity introduced by flooding the elements with mineral oil (to simulate water flooding when fuel elements are changed in GCRE-1). (auth)
Date: September 10, 1958
Creator: Dingee, D. A.; Ballowe, W. C.; Klingensmith, R. W.; Egen, R. A.; Jankowski, F. J. & Chastain, J. W.
Partner: UNT Libraries Government Documents Department