Download Supercritical Pressure Light Water Cooled Reactors full books in PDF, epub, and Kindle. Read online Supercritical Pressure Light Water Cooled Reactors ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
This book focuses on the latest reactor concepts, single pass core and experimental findings in thermal hydraulics, materials, corrosion, and water chemistry. It highlights research on supercritical-pressure light water cooled reactors (SCWRs), one of the Generation IV reactors that are studied around the world. This book includes cladding material development and experimental findings on heat transfer, corrosion and water chemistry. The work presented here will help readers to understand the fundamental elements of reactor design and analysis methods, thermal hydraulics, materials and water chemistry of supercritical water used as a coolant in nuclear power reactors. It will also help readers to broaden their understanding of fundamental elements of light water cooled reactor technologies and the evolution of reactor concepts.
Book Synopsis Supercritical-Pressure Light Water Cooled Reactors by : Yoshiaki Oka
Download or read book Supercritical-Pressure Light Water Cooled Reactors written by Yoshiaki Oka and published by Springer. This book was released on 2014-10-21 with total page 391 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book focuses on the latest reactor concepts, single pass core and experimental findings in thermal hydraulics, materials, corrosion, and water chemistry. It highlights research on supercritical-pressure light water cooled reactors (SCWRs), one of the Generation IV reactors that are studied around the world. This book includes cladding material development and experimental findings on heat transfer, corrosion and water chemistry. The work presented here will help readers to understand the fundamental elements of reactor design and analysis methods, thermal hydraulics, materials and water chemistry of supercritical water used as a coolant in nuclear power reactors. It will also help readers to broaden their understanding of fundamental elements of light water cooled reactor technologies and the evolution of reactor concepts.
Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.
Book Synopsis Super Light Water Reactors and Super Fast Reactors by : Yoshiaki Oka
Download or read book Super Light Water Reactors and Super Fast Reactors written by Yoshiaki Oka and published by Springer Science & Business Media. This book was released on 2010-07-01 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt: Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.
The High Performance Light Water Reactor (HPLWR) is a light water reactor with supercritical steam conditions which has been investigated within the 5th Framework Program of the European Commission. Due to the supercritical pressure of 25 MPa, water, used as moderator and as coolant, flows as a single phase through the core and can be directly fed to the turbine. Using the technology of coal fired power plants with supercritical steam conditions, the heat-up in the core is done in several steps to achieve the targeted high steam outlet temperature of 500 C without exceeding available cladding material limits. Based on a first design of a fuel assembly cluster for a HPLWR with a single pass core, the surrounding internals and the reactor pressure vessel are dimensioned for the first time, following the safety standards of the nuclear safety standards commission in Germany. Furthermore, this design is extended to the incorporation of core arrangements with two and three passes. The design of the internals and the RPV are verified using combined mechanical and thermal stress analyses and thermal-hydraulic analyses."
Book Synopsis High Performance Light Water Reactor - Next Generation Nuclear Power by : Kai Fischer
Download or read book High Performance Light Water Reactor - Next Generation Nuclear Power written by Kai Fischer and published by Sudwestdeutscher Verlag Fur Hochschulschriften AG. This book was released on 2009-11 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The High Performance Light Water Reactor (HPLWR) is a light water reactor with supercritical steam conditions which has been investigated within the 5th Framework Program of the European Commission. Due to the supercritical pressure of 25 MPa, water, used as moderator and as coolant, flows as a single phase through the core and can be directly fed to the turbine. Using the technology of coal fired power plants with supercritical steam conditions, the heat-up in the core is done in several steps to achieve the targeted high steam outlet temperature of 500 C without exceeding available cladding material limits. Based on a first design of a fuel assembly cluster for a HPLWR with a single pass core, the surrounding internals and the reactor pressure vessel are dimensioned for the first time, following the safety standards of the nuclear safety standards commission in Germany. Furthermore, this design is extended to the incorporation of core arrangements with two and three passes. The design of the internals and the RPV are verified using combined mechanical and thermal stress analyses and thermal-hydraulic analyses."
The overall objective of this project is to evaluate the feasibility of supercritical light water cooledreactors for electric power production. The use of light water at supercritical pressures as the coolant in anuclear reactor offers the potential for considerable plant simplification and consequent capital and O & Mcost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamicconditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies for the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as forBWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantiallyshorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a directcycle the steam generators are not needed. If no additional moderator is added to the fuel rod lattice, it ispossible to attain fast neutron energy spectrum conditions in a supercritical water-cooled reactor (SCWR). This type of core can make use of either fertile or fertile-free fuel and retain a hard spectrum to effectivelyburn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity. Onecan also add moderation and design a thermal spectrum SCWR that can also burn actinides. The projectis organized into three tasks.
Book Synopsis Feasibility Study of Supercritical Light Water Cooled Reactors for Electrical Power Production, 5th Quarterly Report, October - December 2002 by : Lawrence Conway
Download or read book Feasibility Study of Supercritical Light Water Cooled Reactors for Electrical Power Production, 5th Quarterly Report, October - December 2002 written by Lawrence Conway and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The overall objective of this project is to evaluate the feasibility of supercritical light water cooledreactors for electric power production. The use of light water at supercritical pressures as the coolant in anuclear reactor offers the potential for considerable plant simplification and consequent capital and O & Mcost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamicconditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies for the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as forBWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantiallyshorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a directcycle the steam generators are not needed. If no additional moderator is added to the fuel rod lattice, it ispossible to attain fast neutron energy spectrum conditions in a supercritical water-cooled reactor (SCWR). This type of core can make use of either fertile or fertile-free fuel and retain a hard spectrum to effectivelyburn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity. Onecan also add moderation and design a thermal spectrum SCWR that can also burn actinides. The projectis organized into three tasks.
Results of the project "High Performance Light Water Reactor--Phase 2," carried out September 2006-February 2010 as part of the 6th European Framework Program.
Book Synopsis High Performance Light Water Reactor by : Thomas Schulenberg
Download or read book High Performance Light Water Reactor written by Thomas Schulenberg and published by KIT Scientific Publishing. This book was released on 2014-07-28 with total page 258 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results of the project "High Performance Light Water Reactor--Phase 2," carried out September 2006-February 2010 as part of the 6th European Framework Program.
Book Synopsis Los mejores peregrinos, y Jerusalem sitiada by :
Download or read book Los mejores peregrinos, y Jerusalem sitiada written by and published by . This book was released on 179? with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Evaluation of a Heavy-water-moderated Boiling-light-water-cooled Reactor by :
Download or read book An Evaluation of a Heavy-water-moderated Boiling-light-water-cooled Reactor written by and published by . This book was released on 1969 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 the supercritical water environment. Reactor pressure vessel Pumps and piping.
Book Synopsis Supercritical Water Reactor (SCWR) - Survey of Materials Research and Development Needs to Assess Viability by :
Download or read book Supercritical Water Reactor (SCWR) - Survey of Materials Research and Development Needs to Assess Viability written by and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 the supercritical water environment. Reactor pressure vessel Pumps and piping.
The supercritical water-cooled reactor (SCWR) is one of the six reactor technologies selected for researchand development under the Generation IV program. SCWRs are promising advanced nuclear systemsbecause of their high thermal efficiency (i.e., about 45% versus about 33% efficiency for current LightWater Reactors [LWRs]) and considerable plant simplification. SCWRs are basically LWRs operating athigher pressure and temperatures with a direct once-through cycle. Operation above the critical pressureeliminates coolant boiling, so the coolant remains single-phase throughout the system. Thus, the need fora pressurizer, steam generators, steam separators, and dryers is eliminated. The main mission of theSCWR is generation of low-cost electricity. It is built upon two proven technologies: LWRs, which arethe most commonly deployed power generating reactors in the world, and supercritical fossil-firedboilers, a large number of which are also in use around the world. The reference SCWR design for the U.S. program is a direct cycle system operating at 25.0 MPa, withcore inlet and outlet temperatures of 280 and 500 C, respectively. The coolant density decreases fromabout 760 kg/m3 at the core inlet to about 90 kg/m3 at the core outlet. The inlet flow splits with about 10%of the inlet flow going down the space between the core barrel and the reactor pressure vessel (thedowncomer) and about 90% of the inlet flow going to the plenum at the top of the rector pressure vessel, to then flow down through the core in special water rods to the inlet plenum. Here it mixes with thefeedwater from the downcomer and flows upward to remove the heat in the fuel channels. This strategy isemployed to provide good moderation at the top of the core. The coolant is heated to about 500 C anddelivered to the turbine. The purpose of this NERI project was to assess the reference U.S. Generation IV SCWR design andexplore alternatives to determine feasibility. The project was organized into three tasks: Task 1. Fuel-cycle Neutronic Analysis and Reactor Core Design Task 2. Fuel Cladding and Structural Material Corrosion and Stress Corrosion Cracking Task 3. Plant Engineering and Reactor Safety Analysis.moderator rods.materials.
Book Synopsis Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production, Nuclear Energy Research Initiative Project 2001-001, Westinghouse Electric Co. Grant Number by : Philip E. MacDonald
Download or read book Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production, Nuclear Energy Research Initiative Project 2001-001, Westinghouse Electric Co. Grant Number written by Philip E. MacDonald and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The supercritical water-cooled reactor (SCWR) is one of the six reactor technologies selected for researchand development under the Generation IV program. SCWRs are promising advanced nuclear systemsbecause of their high thermal efficiency (i.e., about 45% versus about 33% efficiency for current LightWater Reactors [LWRs]) and considerable plant simplification. SCWRs are basically LWRs operating athigher pressure and temperatures with a direct once-through cycle. Operation above the critical pressureeliminates coolant boiling, so the coolant remains single-phase throughout the system. Thus, the need fora pressurizer, steam generators, steam separators, and dryers is eliminated. The main mission of theSCWR is generation of low-cost electricity. It is built upon two proven technologies: LWRs, which arethe most commonly deployed power generating reactors in the world, and supercritical fossil-firedboilers, a large number of which are also in use around the world. The reference SCWR design for the U.S. program is a direct cycle system operating at 25.0 MPa, withcore inlet and outlet temperatures of 280 and 500 C, respectively. The coolant density decreases fromabout 760 kg/m3 at the core inlet to about 90 kg/m3 at the core outlet. The inlet flow splits with about 10%of the inlet flow going down the space between the core barrel and the reactor pressure vessel (thedowncomer) and about 90% of the inlet flow going to the plenum at the top of the rector pressure vessel, to then flow down through the core in special water rods to the inlet plenum. Here it mixes with thefeedwater from the downcomer and flows upward to remove the heat in the fuel channels. This strategy isemployed to provide good moderation at the top of the core. The coolant is heated to about 500 C anddelivered to the turbine. The purpose of this NERI project was to assess the reference U.S. Generation IV SCWR design andexplore alternatives to determine feasibility. The project was organized into three tasks: Task 1. Fuel-cycle Neutronic Analysis and Reactor Core Design Task 2. Fuel Cladding and Structural Material Corrosion and Stress Corrosion Cracking Task 3. Plant Engineering and Reactor Safety Analysis.moderator rods.materials.
The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O & M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed.
Book Synopsis Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production, 3rd Quarterly Report by :
Download or read book Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production, 3rd Quarterly Report written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O & M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed.
