A Utility Assessment Of The Modular High Temperature Gas Cooled Reactor Mhtgr Project 2079
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Utility Industry Evaluation of the Modular High-temperature Gas-cooled Reactor, Project 2079
Author | : Electric Power Research Institute |
Publisher | : |
Total Pages | : |
Release | : 1990 |
Genre | : |
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A Utility/user Summary Assessment of the Modular High Temperature Gas-cooled Reactor Conceptual Design
Author | : Gas Cooled Reactor Associates |
Publisher | : |
Total Pages | : |
Release | : 1987 |
Genre | : Gas cooled reactors |
ISBN | : |
The Modular High-temperature Gas-cooled Reactor (MHTGR).
Author | : |
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Total Pages | : |
Release | : 1986 |
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The MHTGR is an advanced reactor concept being developed in the USA under a cooperative program involving the US Government, the nuclear industry and the utilities. The design utilizes basic HTGR features of ceramic fuel, helium coolant and a graphite moderator. However the specific size and configuration are selected to utilize the inherently safe characteristics associated with these standard features coupled with passive safety systems to provide a significantly higher margin of safety and investment protection than current generation reactors. Evacuation or sheltering of the public is not required. The major components of the nuclear steam supply, with special emphasis on the core, are described. Safety assessments of the concept are discussed.
The Modular High Temperature Gas-cooled Reactor (MHTGR) Containment Trade Study
Author | : |
Publisher | : |
Total Pages | : 0 |
Release | : 1990 |
Genre | : Gas cooled reactors |
ISBN | : |
The modular high temperature gas-cooled reactor (MHTGR) is an advanced reactor concept under development in a cooperative program involving U.S. government, the nuclear industry, and the utilities. The design utilized the basic hig-temperature gas-cooled reactor features of ceramic fuel, helium coolant, and a graphite moderator. The key design parameters, including power, power density, and core and configuration of the MHTGR are selected to utilize the inherent properties of these materials to develop passive safety features that provide a significantly higher margin of safety than current generation reactors. In this paper the reference MHTGR module is combined with several alternatives, each characterized by an alternative containment building structure providing differing degrees of radionuclide containment. The reference design and each alternate are described and their performance compared. The MHTGR radionuclide source and how it related to the radionuclide retention provided by buildings and building features are discussed. This is followed by more detailed considerations leading to the selection of five alternatives. The underlying assumptions and approach employed in assessing alternative designs are summarized. The evaluation of the cost and offsite does reduction benefit of the reference design and selected alternatives are described. Finally, the various alternatives are compared with each other allowing conclusions to be drawn. All design concepts meet the U.S. Environmental Protection Agency's Protective Action Guidelines at the site boundary hence precluding the need for emergency drills, sheltering, or evacuation of the public.
National Energy Security Act of 1991
Author | : United States. Congress. Senate. Committee on Energy and Natural Resources |
Publisher | : |
Total Pages | : 828 |
Release | : 1991 |
Genre | : Energy conservation |
ISBN | : |
MHTGR (Modular High-Temperature Gas-Cooled Reactor) Technology Development Plan
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1988 |
Genre | : |
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This paper presents the approach used to define the technology program needed to support design and licensing of a Modular High-Temperature Gas-Cooled Reactor (MHTGR). The MHTGR design depends heavily on data and information developed during the past 25 years to support large HTGR (LHTGR) designs. The technology program focuses on MHTGR-specific operating and accident conditions, and on validation of models and assumptions developed using LHTGR data. The technology program is briefly outlined, and a schedule is presented for completion of technology work which is consistent with completion of a Final Safety Summary Analysis Report (FSSAR) by 1992.