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The Next Generation Nuclear Plant
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Author :United States. Congress. House. Committee on Government Reform. Subcommittee on Energy and Resources Publisher : ISBN 13 : Total Pages :72 pages Book Rating :4.0/5 ( download)
Book Synopsis The Next Generation Nuclear Plant and Hydrogen Production by : United States. Congress. House. Committee on Government Reform. Subcommittee on Energy and Resources
Download or read book The Next Generation Nuclear Plant and Hydrogen Production written by United States. Congress. House. Committee on Government Reform. Subcommittee on Energy and Resources and published by . This book was released on 2008 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project by :
Download or read book Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R & D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R & D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R & D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R & D activities; and proving selected design components in relevant applications.
Book Synopsis Reducing Risk for the Next Generation Nuclear Plant by :
Download or read book Reducing Risk for the Next Generation Nuclear Plant written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Next Generation Nuclear Plant (NGNP) Project, managed by the Idaho National Laboratory (INL), is directed by the Energy Policy Act of 2005, to research, develop, design, construct, and operate a prototype forth generation nuclear reactor to meet the needs of the 21st Century. As with all large projects developing and deploying new technologies, the NGNP has numerous risks that need to be identified, tracked, mitigated, and reduced in order for successful project completion. A Risk Management Plan (RMP) was created to outline the process the INL is using to manage the risks and reduction strategies for the NGNP Project. Integral to the RMP is the development and use of a Risk Management System (RMS). The RMS is a tool that supports management and monitoring of the project risks. The RMS does not only contain a risk register, but other functionality that allows decision makers, engineering staff, and technology researchers to review and monitor the risks as the project matures.
Book Synopsis The Next Generation Nuclear Plant by :
Download or read book The Next Generation Nuclear Plant written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950°C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.
Book Synopsis Next Generation Nuclear Plant Materials Research and Development Program Plan by : E. L. Shaber
Download or read book Next Generation Nuclear Plant Materials Research and Development Program Plan written by E. L. Shaber and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) designfor the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclearpower for electricity and hydrogen production without greenhouse gas emissions. The reactor design willbe a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor thatwill produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. TheNGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.
Book Synopsis Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP). by :
Download or read book Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP). written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.
Author :United States. Congress. House. Committee on Government Reform. Subcommittee on Energy and Resources Publisher : ISBN 13 : Total Pages :190 pages Book Rating :4.F/5 ( download)
Book Synopsis The Next Generation of Nuclear Power by : United States. Congress. House. Committee on Government Reform. Subcommittee on Energy and Resources
Download or read book The Next Generation of Nuclear Power written by United States. Congress. House. Committee on Government Reform. Subcommittee on Energy and Resources and published by . This book was released on 2005 with total page 190 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Summary for the Next Generation Nuclear Plant Project in Review by :
Download or read book Summary for the Next Generation Nuclear Plant Project in Review written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper reports on the major progress that the NGNP Project has made toward developing and commercializing the HTGR technology. Significant R & D progress has been made in addressing key technical issues for qualification of the HTGR fuel and graphite, codification of high temperature materials and verification and validation of design codes. Work is also progressing in heat transfer/transport design and testing and in development of the high temperature steam electrolysis hydrogen production process. A viable licensing strategy has been formulated in coordination with the NRC and DOE. White papers covering key licensing issues have been and will continue to be submitted and necessary discussions of these key issues have begun with the NRC. Continued government support is needed to complete the Project objectives as established in the 2005 Energy Policy Act.
Book Synopsis Next Generation Nuclear Plant Research and Development Program Plan by :
Download or read book Next Generation Nuclear Plant Research and Development Program Plan written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S Department of Energy (DOE) is conducting research and development (R & D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R & D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R & D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R & D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R & D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R & D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.
Book Synopsis Rapport des douze commissaires, nommés par les quatre Sections de la Commune de Colmar, pour les opérations préliminaires, relatives au partage des Biens communaux by :
Download or read book Rapport des douze commissaires, nommés par les quatre Sections de la Commune de Colmar, pour les opérations préliminaires, relatives au partage des Biens communaux written by and published by . This book was released on 1794 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Next Generation Nuclear Plant Steam Generator and Intermediate Heat Exchanger Materials Research and Development Plan by :
Download or read book Next Generation Nuclear Plant Steam Generator and Intermediate Heat Exchanger Materials Research and Development Plan written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R & D) Program is responsible for performing R & D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Today's high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760°C. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.
Book Synopsis Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4 by :
Download or read book Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4 written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R & D) Program is responsible for performing R & D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R & D Plan include: Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R & D Program. Define and develop inspection needs and the procedures for those inspections. Support selected university materials related R & D activities that would be of direct benefit to the NGNP Project. Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M & C) Project Management Board (PMB). Support document review activities through the Materials Review Committee (MRC) or other suitable forum.
Book Synopsis Le Diogène françois ou les facétieux discours du vray anti-dotour comique blaisois by :
Download or read book Le Diogène françois ou les facétieux discours du vray anti-dotour comique blaisois written by and published by . This book was released on 1617 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site by :
Download or read book Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.
Book Synopsis NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER. by :
Download or read book NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER. written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) plant capable of producing the electricity and high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) application process, as recommended in the Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy. NRC licensing of the NGNP plant utilizing this process will demonstrate the efficacy of licensing future HTGRs for commercial industrial applications. This white paper is one in a series of submittals that will address key generic issues of the COL priority licensing topics as part of the process for establishing HTGR regulatory requirements.
Book Synopsis The Next Generation Nuclear Plant - Insights Gained from the INEEL Point Design Studies by : R. L. Moore
Download or read book The Next Generation Nuclear Plant - Insights Gained from the INEEL Point Design Studies written by R. L. Moore and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper provides the results of an assessment of two possible versions of the Next GenerationNuclear Plant (NGNP), a prismatic fuel type helium gas-cooled reactor and a pebble-bed fuel helium gasreactor. Insights gained regarding the strengths and weaknesses of the two designs are also discussed. Both designs will meet the three basic requirements that have been set for the NGNP: a coolant outlettemperature of 1000 C, passive safety, and a total power output consistent with that expected forcommercial high-temperature gas-cooled reactors. Two major modifications of the current Gas Turbine-Modular Helium Reactor (GT-MHR) design were needed to obtain a prismatic block design with a 1000 Coutlet temperature: reducing the bypass flow and better controlling the inlet coolant flow distribution to thecore. The total power that could be obtained for different core heights without exceeding a peak transientfuel temperature of 1600 °C during a high or low-pressure conduction cooldown event was calculated. With a coolant inlet temperature of 490 °C and 10% nominal core bypass flow, it is estimated that the peakpower for a 10-block high core is 686 MWt, for a 12-block high core is 786 MWt, and for a 14-block coreis about 889 MWt. The core neutronics calculations showed that the NGNP will exhibit strongly negativeDoppler and isothermal temperature coefficients of reactivity over the burnup cycle. In the event of rapidloss of the helium gas, there is negligible core reactivity change. However, water or steam ingress into thecore coolant channels can produce a relatively large reactivity effect. Two versions of an annular pebble-bed NGNP have also been developed, a 300 and a 600 MWt module. From this work we learned how to design passively safe pebble bed reactors that produce more than 600MWt. We also found a way to improve both the fuel utilization and safety by modifying the pebble design(by adjusting the fuel zone radius in the pebble to optimize the fuel-to-moderator ratio). We also learnedhow to perform design optimization calculations by using a genetic algorithm that automatically selects asequence of design parameter sets to meet specified fitness criteria increasingly well. In the pebble-bedNGNP design work, we use the genetic algorithm to direct the INEEL's PEBBED code to performhundreds of code runs in less than a day to find optimized design configurations. And finally, we learnedhow to calculate cross sections more accurately for pebble bed reactors, and we identified research needsfor the further refinement of the cross section calculations.
Book Synopsis Ein Apostolischer, liebreicher, Trewhertziger vnd Ernstlicher Sendbrieff der Fürsten der Apostel Petri vnd Pauli, ane den aller Heyligsten Herrn, Herrn Pauln den Fünfften dises namens Babsten vnnd Bischoffen zu Rom etc by :
Download or read book Ein Apostolischer, liebreicher, Trewhertziger vnd Ernstlicher Sendbrieff der Fürsten der Apostel Petri vnd Pauli, ane den aller Heyligsten Herrn, Herrn Pauln den Fünfften dises namens Babsten vnnd Bischoffen zu Rom etc written by and published by . This book was released on 1607 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
