3 Matching Results

Search Results

Advanced search parameters have been applied.

SCWR - Safety Systems and Containment Investigations - Summary Report

Description: The design of the Generation IV Supercritical Water Reactor (SCWR) was reviewed. The general design criteria and safety requirements were specified to provide a basis for the design of the safety systems and the containment. A combination of the most stringent requirements applied today is used. The majority of the effort was devoted to developing the preliminary design of a reactor core cooling system that mitigates the consequences of loss of feedwater events.
Date: September 8, 2004
Creator: Jonsson, Nils-Olov
Partner: UNT Libraries Government Documents Department

Supercritical Water Reactor (SCWR) - Survey of Materials Research and Development Needs to Assess Viability

Description: Supercritical water-cooled reactors (SCWRs) are among the most promising advanced nuclear systems because of their high thermal efficiency [i.e., about 45% vs. 33% of current light water reactors (LWRs)] and considerable plant simplification. SCWRs achieve this with superior thermodynamic conditions (i.e., high operating pressure and temperature), and by reducing the containment volume and eliminating the need for recirculation and jet pumps, pressurizer, steam generators, steam separators and dryers. The reference SCWR design in the U.S. is a direct cycle, thermal spectrum, light-water-cooled and moderated reactor with an operating pressure of 25 MPa and inlet/outlet coolant temperature of 280/500 °C. The inlet flow splits, partly to a down-comer and partly to a plenum at the top of the reactor pressure vessel to flow downward through the core in special water rods to the inlet plenum. This strategy is employed to provide good moderation at the top of the core, where the coolant density is only about 15-20% that of liquid water. The SCWR uses a power conversion cycle similar to that used in supercritical fossil-fired plants: high- intermediate- and low-pressure turbines are employed with one moisture-separator re-heater and up to eight feedwater heaters. The reference power is 3575 MWt, the net electric power is 1600 MWe and the thermal efficiency is 44.8%. The fuel is low-enriched uranium oxide fuel and the plant is designed primarily for base load operation. The purpose of this report is to survey existing materials for fossil, fission and fusion applications and identify the materials research and development needed to establish the SCWR viabilitya with regard to possible materials of construction. The two most significant materials related factors in going from the current LWR designs to the SCWR are the increase in outlet coolant temperature from 300 to 500 °C and the possible compatibility issues associated with ...
Date: September 1, 2003
Creator: MacDonald, Philip E.
Partner: UNT Libraries Government Documents Department

A Parametric Study of the Thermal-Hydraulic Response of Supercritical Light Water Reactors During Loss-of-Feedwater and Turbine-Trip Events

Description: The Idaho National Engineering and Environmental Laboratory in investigating the feasibility of supercritical light water reactors for low-cost electric power production through a Nuclear Energy Research Initiative Project sponsored by the United State Department of Energy. The project is evaluating a variety of technical issues related to the fuel and reactor design, material corrosion, and safety characteristics. This paper presents the results of parametric calculations using the RELAP5 computer code to characterize the thermal-hydraulic response of supercritical reactors to transients initiated by loss-of-feedwater and turbine-trip events. The purpose of the calculations was to aid in the design of the safety systems by determining the time available for the safety systems to respond and their required capacities.
Date: September 1, 2003
Creator: Davis, Cliff B.; Buongiorno, Jacopo & MacDonald, Philip E.
Partner: UNT Libraries Government Documents Department