Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
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Showing 1 to 17 of 17 for “"SCWR"”.
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Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.
… discontinuity factors for the next-generation PT-SCWR flux calculations. Results show that using GET in conjunction with leakage corrections yields substantial improvements in accuracy over standard homogenization and should be given serious consideration as a method for performing neutronic …
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Communication protocols, queuing and scheduling delay analysis in CANDU SCWR hydrogen co-generation model
… Uranium-Super Critical Water Reactor (CANDU-SCWR) hydrogen plant and a discrete-time controller, sensor and actuator block, that are connected via a communication network, such as e.g. controller area network (CAN), Ethernet or wireless networks. Issues associated with NCSs are time-varying …
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Thermal aspects of high efficiency channel with conventional and alternative fuels in SuperCritical water-cooled reactor (SCWR) applications
… concepts, SuperCritical Water-cooled Reactors (SCWRs) are expected to have high thermal efficiencies within the range of 45 ‒ 50% owing to reactor‘s high outlet temperatures. A generic pressure-channel (or pressure-tube)SCWR operates at a pressure of 25 MPa with inlet- and outlet-coolant …
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Stability analysis of supercritical water cooled reactors
The Supercritical Water-Cooled Reactor (SCWR) is a concept for an advanced reactor that will operate at high pressure (25MPa) and high temperature (500°C average core exit). The high coolant temperature as it leaves the reactor core gives the SCWR the potential for high thermal efficiency (45%). …
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Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications
… SuperCritical Water-cooled nuclear Reactor (SCWR) concepts. Thus, this new correlation, for forced convective heat transfer in the normal heat-transfer regime, can be used for preliminary heat-transfer calculations in SCWR fuel channels. It has demonstrated a good fit for Heat Transfer …
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Design of a fault tolerant control scheme based on sliding mode for Canadian supercritical water reactor
Canadian Super Critical Water Reactor (SCWR) is one of the Generation IV reactor types and possible heat source for co-hydrogen production through copper chlorine thermochemical cycle. To maintain the balance between the hydrogen production and electricity production effectively and to utilize the …
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Conceptual development and analysis of multiple integrated hydrogen production plants with Cu-Cl cycle
… Cu-Cl cycle. The second system consists of SCWR, hydrogen fueled combined cycle, compression system and five-step Cu-Cl cycle. The third system consists of solar heliostat steam generator, Rankine cycle, compression system and five-step Cu-Cl cycle. The fourth system consists of SCWR, …
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Numerical Investigations of the Fluid Flow and Heat Transfer and Construction of Control System for the Canadian Supercritical Water-Cooled Reactor Power Plant
… with the Supercritical Water-Cooled Reactor (SCWR) concept. This work focuses on the numerical studies of the fluid flow and heat transfer of the supercritical water in the nuclear reactor fuel bundle, and the construction of the linear dynamic model and the design of the control system for …
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Transmutation rates in the annulus gas of pressure tube water reactors
… Pressure Tube Supercritical Water Reactor (PT SCWR) fuel channel models have been developed in Monte Carlo N-Particle (MCNP) code. Neutron fluxes in the fuel channel annulus gas have been obtained by simulating different types of neutron sources in both PTR and PT SCWR fuel channels. …
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Specifics of forced-convection heat transfer in a vertical 7-element bundle cooled with upward flow of SuperCritical Water
… investigating the SuperCritical Water Reactor (SCWR) concept. However, determining Heat Transfer specifics for SuperCritical Water in bundle configurations is required. Many empirical Nusselt number (Nu) correlations derived from bare tubes are available, with only one derived from a bundle. No …
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Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs)
… six Generation‒IV nuclear-reactor concepts, the SCWRs are expected to have high thermal efficiencies within the range of 40 ‒ 50% owing to reactor’s high outlet temperatures. The Canadian pressure-tube-type SCWR is featured with 3-batch refueling, 336 vertical fuel channels, a porous ceramic …
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Materiály pro reaktory IV. generace
… je popis vybraných reaktorů IV. generace – VHTR, SCWR a MSR z hlediska jejich materiálových požadavků s důrazem na reaktor VHTR. V práci je popsán základní princip vysokoteplotního reaktoru a jeho základní uspořádání konstrukčních částí z hlediska materiálového namáhání. Ve střední pasáži jsou …
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Heat transfer to supercritical water flowing in short vertical bare tube and rod-bundle geometries
… efficiency, SuperCritical Water-cooled Reactors (SCWRs) and SuperCritical-Pressure-Small Modular Reactors (SCP-SMRs) operate at supercritical pressures, requiring detailed studies of Heat Transfer (HT). This research investigates experimental data from vertical bare tubes and rod-bundle geometries …
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Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility
The SuperCritical Water-cooled nuclear Reactor (SCWR) is one of six Generation-IV nuclear-reactor concepts currently being designed. It will operate at pressures of 25 MPa and temperatures up to 625°C. These operating conditions make a SuperCritical Water (SCW) Nuclear Power Plant (NPP) suitable to …
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CFD determination of fluid and geometry related localized heat transfer phenomena for supercritical water flow
… concept of Supercritical Water-cooled Reactor (SCWR) as part of the Generation IV International Forum aims to improve the thermal efficiency over current power plants by utilizing cooling water at pressures and temperature above the critical point. At supercritical conditions, however, the …
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Conceptual design for a re-entrant type fuel channel for supercritical water-cooled nuclear reactors
… a CANDU-type SuperCritical Water-Cooled Reactor (SCWR) is to eliminate the annulus gap and use a ceramic insert to insulate the coolant from the moderator. While such a design may work, alternative fuel-channel design concepts are under development to explore the optimum efficiency of SCWRs. One …
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Study of heat transfer in a 7-element bundle cooled with the upward flow of supercritical Freon-12
… SuperCritical Water-cooled nuclear Reactor (SCWRs) designs cannot be finalized without such data. Therefore, as a preliminary approach experiments in SCW-cooled bare tubes and in bundles cooled with SC modeling fluids can be used. One of the SC modeling fluids typically used is Freon-12 …