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Benchmark Specifications and Data Requirements for Initial Modeling of the China Experimental Fast Reactor.

Description: A specification is proposed for an initial transient benchmark analysis of the China Experimental Fast Reactor design based on the analysis capabilities of the SAS4A/SASSYS-1 code. For the initial benchmark, a single-channel protected transient overpower accident is defined. Reactivity feedback coefficients will not be required and simplified material properties are recommended. This report also describes the data required for developing the modeling input. This data includes assembly geometry,… more
Date: June 4, 2010
Creator: Fanning, T. H. & Division, Nuclear Engineering
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of Boron Dilution Transients in PWRS.

Description: A study has been carried out with PARCS/RELAP5 to understand the consequences of hypothetical boron dilution events in pressurized water reactors. The scenarios of concern start with a small-break loss-of-coolant accident. If the event leads to boiling in the core and then the loss of natural circulation, a boron-free condensate can accumulate in the cold leg. The dilution event happens when natural circulation is re-established or a reactor coolant pump (RCP) is restarted in violation of opera… more
Date: February 4, 2004
Creator: Diamond, David J.; Bromley, Blair P. & Aronson, Arnold L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Half-plant zeta potential test. Final report

Description: With the exception of N Reactor, the production reactors operated by Douglas United Nuclear, Inc., use treated Columbia River water as the coolant on a once-through basis. Thus, radionuclides formed largely by the neutron activation of river salts are discharged to the river. One method of reducing the quantity of radionuclides in the effluent is to increase the efficiency of parent isotope removal during the coolant treatment process. Prior to 1961 the water treatment process had been improved… more
Date: December 4, 1967
Creator: Geier, R. G. & Wells, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical heat flux and boiling heat transfer to water in a 3-mm-diameter horizontal tube.

Description: Boiling of the coolant in an engine, by design or by circumstance, is limited by the critical heat flux phenomenon. As a first step in providing relevant engine design information, this study experimentally addressed both rate of boiling heat transfer and conditions at the critical point of water in a horizontal tube of 2.98 mm inside diameter and 0.9144 m heated length. Experiments were performed at system pressure of 203 kPa, mass fluxes in range of 50 to 200 kg/m{sup z}s, and inlet temperatu… more
Date: December 4, 2000
Creator: Yu, W.; Wambsganss, M. W.; Hull, J. R. & France, D. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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