Download or read book A Particle bed Gas Cooled Fast Reactor Core Design for Waste Minimization written by and published by . This book was released on 2002 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: The issue of waste minimization in advanced reactor systems has been investigated using the Particle-Bed Gas-Cooled Fast Reactor (PB-GCFR) design being developed and funded under the U.S. Department of Energy Nuclear Energy Research Initiative (USDOE NERI) Program. Results indicate that for the given core power density and constraint on the maximum TRU enrichment allowable, the lowest amount of radiotoxic transuranics to be processed and hence sent to the repository is obtained for long-life core designs. Calculations were additionally done to investigate long-life core designs using LWR spent fuel TRU and recycle TRU, and different feed, matrix and reflector materials. The recycled TRU and LWR spent TRU fuels give similar core behaviors, because of the fast spectrum environment which does not significantly degrade the TRU composition. Using light elements as reflector material was found to be unattractive because of power peaking problems and large reactivity swings. The application of a lead reflector gave the longest cycle length and lowest TRU processing requirement. Materials compatibility and performance issues require additional investigation.
Download or read book Particle bed Gas cooled Fast Reactor PB GCFR Design Project Final Technical Report Sept 2001 Aug 2003 written by and published by . This book was released on 2003 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of this project is to develop a conceptual design of a particle-bed, gas-cooled fast reactor (PB-GCFR) core that meets the advanced reactor concept and enhanced proliferation-resistant goals of the US Department of Energy's NERI program. The key innovation of this project is the application of a fast neutron spectrum environment to enhance both the passive safety and transmutation characteristics of the advanced particle-bed and pebble-bed reactor designs. The PB-GCFR design is expected to produce a high-efficiency system with a low unit cost. It is anticipated that the fast neutron spectrum would permit small-sized units ((almost equal to) 150 MWe) that can be built quickly and packaged into modular units, and whose production can be readily expanded as the demand grows. Such a system could be deployed globally. The goals of this two-year project are as follows: (1) design a reactor core that meets the future needs of the nuclear industry, by being passively safe with reduced need for engineered safety systems. This will entail an innovative core design incorporating new fuel form and type; (2) employ a proliferation-resistant fuel design and fuel cycle. This will be supported by a long-life core design that is refueled infrequently, and hence, reduces the potential for fuel diversion; (3) incorporate design features that permit use of the system as an efficient transmuter that could be employed for burning separated plutonium fuel or recycled LWR transuranic fuel, should the need arise; and (4) evaluate the fuel cycle for waste minimization and for the possibility of direct fuel disposal. The application of particle-bed fuel provides the promise of extremely high burnup and fission-product protection barriers that may permit direct disposal.
Download or read book An Evaluation of the Gas Cooled Fast Reactor written by U.S. Atomic Energy Commission. Division of Reactor Development and Technology and published by . This book was released on 1972 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book An Evaluation of Gas cooled Fast Reactor written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 260 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Gas Cooled Pebble Bed Reactor for a Large Central Station written by and published by . This book was released on 1957 with total page 324 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Randomly Packed Settled Bed Fast Reactor Concept written by L. Green and published by . This book was released on 1966 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Preliminary Study of a Fast Reactor Core Test Facility written by D. B. Hall and published by . This book was released on 1959 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Analysis of an Advanced Gas cooled Fast Reactor Core Design written by Patrick John Heher and published by . This book was released on 2006 with total page 272 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Gas cooled Reactor Program Quarterly Progress Report for Period Ending written by Oak Ridge National Laboratory and published by . This book was released on 1960-03-31 with total page 282 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Ordered bed Fast Reactor Concept 1000 MW e Reactor Design written by and published by . This book was released on 1966 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Feasibility Study of a 1000 Mwe Sodium cooled Fast Reactor Research and development program written by North American Aviation. Atomics International Division and published by . This book was released on 1966 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Outline of Monju Improved Design III written by and published by . This book was released on 1979 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Safety and Core Design of Large Liquid metal Cooled Fast Breeder Reactors written by Staffan Alexander Qvist and published by . This book was released on 2013 with total page 650 pages. Available in PDF, EPUB and Kindle. Book excerpt: In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions from human activities, the world is in ever more desperate need of new, inexhaustible, safe and clean primary energy sources. A viable solution to this problem is the widespread adoption of nuclear breeder reactor technology. Innovative breeder reactor concepts using liquid-metal coolants such as sodium or lead will be able to utilize the waste produced by the current light water reactor fuel cycle to power the entire world for several centuries to come. Breed & burn (B & B) type fast reactor cores can unlock the energy potential of readily available fertile material such as depleted uranium without the need for chemical reprocessing. Using B & B technology, nuclear waste generation, uranium mining needs and proliferation concerns can be greatly reduced, and after a transitional period, enrichment facilities may no longer be needed. In this dissertation, new passively operating safety systems for fast reactors cores are presented. New analysis and optimization methods for B & B core design have been developed, along with a comprehensive computer code that couples neutronics, thermal-hydraulics and structural mechanics and enables a completely automated and optimized fast reactor core design process. In addition, an experiment that expands the knowledge-base of corrosion issues of lead-based coolants in nuclear reactors was designed and built. The motivation behind the work presented in this thesis is to help facilitate the widespread adoption of safe and efficient fast reactor technology.
Download or read book Risk informed Design Guidance for a Generation IV Gas cooled Fast Reactor Emergency Core Cooling System written by Michael James Delaney and published by . This book was released on 2004 with total page 117 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fundamental objectives of sustainability, economics, safety and reliability, and proliferation resistance, physical protection and stakeholder relations must be considered during the design of an advanced reactor. However, an advanced reactor's core damage frequency dominates all other considerations at the preliminary stage of reactor design. An iterative four-step methodology to guide the MIT gas-cooled fast reactor emergency core cooling system design through PRA insights was utilized based upon the preliminary stage of the reactor design and activities currently ongoing in the nuclear industry, regulator, and universities regarding advanced reactors. Advanced reactor designs also face an uncertain regulatory environment. It was concluded from the move towards risk- informed regulations of current reactors, that there will be some level of probabilistic insights in the regulations and supporting regulatory documents for advanced, "Generation-IV" nuclear reactors. The four-step methodology is moreover used to help designers analyze designs under potential risk-informed regulations and predict design justifications the regulator will require during the licensing process. The iterative design guidance methodology led to a reduction of the CDF contribution due to a LOCA of over three orders of magnitude from the baseline ECCS design (from 1.19x10-5 to 6.48x10-8 for the 3x100% loop configuration) and potential ECCS licensing issues were identified. This illustrates the value of formal design guidance based upon PRA.
Download or read book Gas cooled Fast Reactor written by and published by . This book was released on 2007* with total page 1 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Integral Fast Reactor A Practical Approach to Waste Management written by and published by . This book was released on 1993 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Core Design for High temperature Gas cooled Reactors written by Kerntechnischer Ausschuss, Köln and published by . This book was released on 1986 with total page 4 pages. Available in PDF, EPUB and Kindle. Book excerpt:
