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Valve Operating System System Description No. 10

Description: A description is given of the valve operating system for the PWR. The valves served by this system are a component pant of the following systems: reactor coolant system; pressurizer and pressure relief system; coolant discharge and vent system; and failed element detection and location system. (W.L.H.)
Date: May 1, 1957
Partner: UNT Libraries Government Documents Department

Monthly Progress Report for the Period August 1 to 31, 1958

Description: plants ln England and France. With the increasing de output of given designs and probably allow operation at higher polymer contents than orignally foreseen, thereby reducing the make-up requirements. The physical characteristics of the OMRE such as critical loading, temperature coefficient, and general stability appeared to be close to the predicted values. Radiation levels in the primary circuit area during full power operation appear to be so low that maintenance is possible during operation. The reactor has been run for a full month at 30% polymer concentration and is, at the time of this writing, brought to a still higher steady state percentage of breakdown products ln the coolant stream. No evidence whatsoever of fouling or precipitation has been observed. The reactor behaves in a routine manner in all respects and invites immediate application of the OMR principle to reactors for large scale ceniral stations. Final design on one 11.4 Mwe unit for the city of Piqua, Ohio, has now stanted. A short description is given of OMR power reactors. The use of magnetic jack mechanisms for control and safety rods provides a reactors top shield without penetrations, as well as an unpenetrated lower core vessel, still avoiding any interference from the control rods during fuel changing. The new finned-plate fuel element is mentioned as well as the use of a liquid pressurizing pump instead of nitrogen gas pressurization. It is conservatively predicted that the cost of organic liquid make-up for these designs will not contribute more than one half to one mill per kwh to the total power cost. In case operation at higher polymer concentrations appears practicable, this figure may even be lower. More detailed pricing informntion available now, has shown that the original cost estimate of around 0 per kw installed for a 150 Mwe plant can ...
Date: September 20, 1958
Creator: Garbe, R. W. & Walchli, H. E.
Partner: UNT Libraries Government Documents Department

Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

Description: Design criteria are presented for liquid-metal loop facilities for the Advanced Test Reactor. It was concluded that achievement of the design objectives could not be predicted with any high degree of confidence when utilizing the package loop concept based on the design philosophy of the PW-19 loop. (M.C.G.)
Date: July 1, 1962
Partner: UNT Libraries Government Documents Department

TRIP TO ALCO PRODUCTS, KAPL, COMBUSTION ENGINEERING CO. AND FT. BELVOIR (APPR). RE: COOLING WATER ACTIVITY BUILDUP IN PRESSURIZED WATER REACTORS

Description: Several uncertainties associated with predicting activity levels in water-cooled reactors are discussed in connection with development of the Nuclear Merchant Ship Reactor (Maritime Pressurized Water Reactor). (T.R.H.)
Date: August 1, 1958
Creator: Culver, H.N.
Partner: UNT Libraries Government Documents Department

REACTOR PLANT SELF-ACTUATED RELIEF VALVE OPERATION. CORE 1, SEED 1. Test Results T-643700

Description: The relief valves that were tested included four each in the reactor coolant loop and in the purification system. Test results are tabulated which indicated that all valves operated at or witai the prescribed limits of 2530 plus or minus 50 psig in the "as left" condition. Most of the valves had to be popped and adjusted several times befors the valves would pop at a pressure within the prescribed limitations. Some of the difficulties encountered during the testing are discussed. (B.O.G.)
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department

Mathematical modeling of a Fermilab helium liquefier coldbox

Description: Fermilab Central Helium Liquefier (CHL) facility is operated 24 hours-a-day to supply 4.6{degrees}K for the Fermilab Tevatron superconducting proton-antiproton collider Ring and to recover warm return gases. The centerpieces of the CHL are two independent cold boxes rated at 4000 and 5400 liters/hour with LN{sub 2} precool. These coldboxes are Claude cycle and have identical heat exchangers trains, but different turbo-expanders. The Tevatron cryogenics demand for higher helium supply from CHL was the driving force to investigate an installation of an expansion engine in place of the Joule-Thompson valve. A mathematical model was developed to describe the thermo- and gas-dynamic processes for the equipment included in the helium coldbox. The model is based on a finite element approach, opposite to a global variables approach, thus providing for higher accuracy and conversion stability. Though the coefficients used in thermo- and gas-dynamic equations are unique for a given coldbox, the general approach, the equations, the methods of computations, and most of the subroutines written in FORTRAN can be readily applied to different coldboxes. The simulation results are compared against actual operating data to demonstrate applicability of the model.
Date: December 1, 1995
Creator: Geynisman, M.G. & Walker, R.J.
Partner: UNT Libraries Government Documents Department

Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor

Description: Results of the design criteria work performed prior to the termination of work on the package concept for the liquid metal loop facilities for the Advanced Test Reactor are summarized. Based on the results of the criteria studies, it was concluded that achievement of the design objectives could not be predicted with any high degree of confidence when utilizing the package loop concept based on the design philosophy of the PW-19 loop. The characteristics of the loop are given along with design and development accomplishments for associated equipment. (N.W.R.)
Date: March 1, 1963
Partner: UNT Libraries Government Documents Department

CONCEPTUAL DESIGN OF A VAPOR VOLUME FRACTION INSTRUMENT

Description: The preliminary design is described of equipment to carry out experiments on boiling burnout in which the average coolant density as a function of coolant channel length as well as local coolant densities may be measured. It appears that by use of the equipment, average densities can be accomplished in a few seconds, while determination of a complete density map (with 5% error) across a plane of the assembly requires approximately one hour. (J.R.D.)
Date: April 5, 1961
Creator: Kalos, M.H.; Davis, S.A.; Mittelman, P.S. & Mastras, P.
Partner: UNT Libraries Government Documents Department

GCR-ORR LOOP NO. 2 FILTER TESTS. PART II

Description: Tests of Cambridge absolute filters, Model Sl-071, specified for use in the GCR-ORR Loop No. 2 as full-flow, primary coolant fiiters were completed. kD.O.P/ (dioctylphthalate) efficiency tests were performed on three filters in the as-received condition, on two filters following canning and thermal cycling, and on one of the canned fiIters following bsking out. None of the three units met the design criteria of 99.97% efficiency for removal of 0.3 micron particles in the as-received condition. The postthermal cycle efficiencies of the canned fiIters were slightly higher than their respective as-received efficiencies. At the corapletion of testing, the two fiiters canned for installation in the reactor facility had measured efficiencies of 99.855% and 99.93%. These values were judged acceptable for the intended application/su The thermal cycling of the two canned filters and the subsequent baking out of one of these units demonstrated that a limited amount of off-gas products would be given off/su Pressure drop tests were performed on the canned fiiters with instrument air (ambient temperature, atmospheric pressure) over a flow rate range of 150 to 530 lb/hr. Curves of pressure drop across each fiIter versus Reynolds number were plotted for air and He. (auth)
Date: February 19, 1962
Creator: Flint, F.A. & Smith, A.M.
Partner: UNT Libraries Government Documents Department

PRESSURE EQUALIZATION BY FLUID EXCHANGE BETWEEN PARALLEL FLOW CHANNELS

Description: Hydraulic and deflection analyses of the unequal flow passages in the HFIR control region revealed excessive pressure differentials. A proposal to drill connecting holes between the flow passages initiated an experimental program for investigating the effectiveness crossflow on pressure equalization. Empirical constants for an analytical model and experimental design data on reduction of pressure differentials between channels were obtained. It was determined that crossflow between channels would satisfactorily reduce the pressure differentials. (auth)
Date: April 1, 1963
Creator: Chapman, T.G. & Stevens, P.N.
Partner: UNT Libraries Government Documents Department

PRELIMINARY HAZARDS EVALUATION OF THE ISOLATED COOLANT LOOPS IN THE HWCTR

Description: The design features of two isolated coolant loops in the Heavy Water Components Test Reactor (HWCTR) and the effect of these features on reactor safety are described. It is shown that limitations on the operating conditions, backed up by properly chosen safety systems, will permit operation of the loops without adding appreciably to the reactor hazards. (auth)
Date: July 1, 1960
Creator: Arnett, L.M.; Parkinson, T.F.; Randall, D. & Ross, C.P.
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

A FLOW VISUALIZATION LOOP FOR FLOW PATTERN STUDIES IN REACTOR MODELS

Description: The installation of a milling yellow flow visualization loop has been completed. Milling yellow is an organic dye which when dissolved in water exhibits flow double refracting properties that permit visual observations of flow patterns. The equipment is to be used in qualitative studies of flow patterns in various models of reactor vessels and components. (auth)
Date: August 1, 1958
Creator: Mixon, W.R. & MacColl, H.A.
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