Author: P. M. WilliamsPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages :
Book Description
Draft Preapplication Safety Evaluation Report for the Modular High-temperature Gas-cooled Reactor
Author: P. M. WilliamsPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages :
Book Description
Draft Preapplication Safety Evaluation Report for Power Reactor Inherently Safe Module Liquid Metal Reactor
Author: R. R. LandryPublisher:
ISBN:
Category : Liquid metal cooled reactors
Languages : en
Pages :
Book Description
Preapplication Safety Evaluation Report for the Power Reactor Innovative Small Module (PRISM) Liquid-metal Reactor. Final Report
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 422
Book Description
This preapplication safety evaluation report (PSER) presents the results of the preapplication desip review for die Power Reactor Innovative Small Module (PRISM) liquid-mew (sodium)-cooled reactor, Nuclear Regulatory Commission (NRC) Project No. 674. The PRISM conceptual desip was submitted by the US Department of Energy in accordance with the NRC's ''Statement of Policy for the Regulation of Advanced Nuclear Power Plants'' (51 Federal Register 24643). This policy provides for the early Commission review and interaction with designers and licensees. The PRISM reactor desip is a small, modular, pool-type, liquid-mew (sodium)-cooled reactor. The standard plant design consists of dim identical power blocks with a total electrical output rating of 1395 MWe- Each power block comprises three reactor modules, each with a thermal rating of 471 MWt. Each module is located in its own below-grade silo and is co to its own intermediate heat transport system and steam generator system. The reactors utilize a metallic-type fuel, a ternary alloy of U-Pu-Zr. The design includes passive reactor shutdown and passive decay heat removal features. The PSER is the NRC's preliminary evaluation of the safety features in the PRISM design, including the projected research and development programs required to support the design and the proposed testing needs. Because the NRC review was based on a conceptual design, the PSER did not result in an approval of the design. Instead it identified certain key safety issues, provided some guidance on applicable licensing criteria, assessed the adequacy of the preapplicant's research and development programs, and concluded that no obvious impediments to licensing the PRISM design had been identified.
Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission in the Matter of Cincinnati Gas and Electric Company, William H. Zimmer Nuclear Power Station, Unit 1, Docket No. 50-358
Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor RegulationPublisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 672
Book Description
Safety Evaluation Report
Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor RegulationPublisher:
ISBN:
Category : Nuclear facilities
Languages : en
Pages : 288
Book Description
High-temperature Gas-cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report
Author: Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 30
Book Description
Bref narré de ce qui s'est passé en suite du different meu entre l'evesque de Chalcedoine, delegué du Pape aux Royaume d'Angleterre et d'Ecosse et les Jesuites Anglois
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
High-temperature Gas-cooled Reactor Safety Studies for the Division of Reactor Safety Research
Author: Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 40
Book Description
Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.
High-temperature Gas-cooled Reactor Safety Studies for the Division of Accident Evaluation Quarterly Progress Report, January 1-March 31, 1985
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Modeling, code development, and analyses of the modular High-Temperature Gas-Cooled Reactor (HTGR) continued with work on the side-by-side design. Fission-product release and transport experiments were completed. A description and assessment report on Oak Ridge National Laboratory HTGR safety codes was issued.
