• Sodium Cooled Reactors
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Fluoride Salt Cooled Reactor Primary Flowmeter Based on N-16 and/or F-20 Decays Fluoride Salt Cooled Reactor Primary Flowmeter Based on N-16 and/or F-20 Decays Disclosure Number 201303032 Technology Summary Measuring the primary coolant flow in a Fluoride salt-cooled High-temperature Reactor (FHR) is required to operate the plant. Particularly harsh environme…

POWER CYCLE AND STRESS ANALYSES FOR HIGH TEMPERATURE GAS-COOLED REACTOR This is a preprint of a paper intended for publication in a journal or proceedings. Since changes may be made before publication, this preprint should not be cited or reproduced without permission of the author. This document was prepared as an account of work sponsored by an agency of the United States Government. Ne…

Deep Burn: Development of Transuranic Fuel for High-Temperature Helium-Cooled Reactors- Monthly Highlights September 2010 ORNL/TM-2010/252 September 2010 Deep Burn: Development of Transuranic Fuel for High-Temperature Helium-Cooled Reactors Monthly Highlights TRISO-Coated Particle with Mixed Pu, Th Oxide Ke…

: Metal, Fission, model...

Advanced High Temperature Reactor Systems and Economic Analysis ORNL/TM-2011/364 Advanced High Temperature Reactor Systems and Economic Analysis September 2011 Status Rev 0 September 30, 2011 Prepared by D. E. Holcomb F. J. Peretz A. L. Qualls DOCUMENT AVAILABILITY Reports pr…

Temperature initiated passive cooling system Description FIELD OF THE INVENTION The present invention relates to passive cooling systems, and more particularly to passive cooling systems which rely on the thermodynamic critical point temperature of a heat transfer fluid to initiate the cooling process. BACKGROUND OF THE INVENTION Conventional passive cooling systems are usually…

Deep Burn: Development of Transuranic Fuel for High-Temperature Helium-Cooled Reactors- Monthly Highlights October 2010 ORNL/TM-2010/300 October 2010 Deep Burn: Development of Transuranic Fuel for High-Temperature Helium-Cooled Reactors Monthly Highlights TRISO-Coated Particle with Mixed Pu, Th Oxide Kernel…

Next Generation Nuclear Plant GAP Analysis Report ORNL/TM-2007/228 Next Generation Nuclear Plant GAP Analysis Report July 2008 Prepared by S. J. Ball R&D Staff Member DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of…

The licensing experinece of the Modular High-Temperature Gas-Cooled Reactor (MHTGR) GA--A19455 DE88 017341 THE LICENSING EXPERIENCE OF THE MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR (MHTGR) by F.A. SILADY, J.C. CUNLIFFE, and L.P. WALKER DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Gover…

NGNP Point Design - Results of the Initial Neutronics and Thermal-Hydraulic Assessments During FY-03, Rev. 1 INEEL/EXT-03-00870 Revision 1 NGNP Point Design Results of the Initial Neutronics and Thermal- Hydraulic Assessments During FY-03 September 2003 Idaho National Engineering and Environmental Laboratory Bechtel BWXT Idaho, LLC INEEL/EXT-03-00870 Rev. 1 NGNP Preliminary Po…

Shielding assessment for the proposed HRIBF upgrade to the National ISOL Facility t t 1 ORNUTM-13366 RECEIV APR 2 9 1997 O S T I Shielding Assessment for the Proposed HRIBF Upgrade to the National ISOL Facility C. 0. Slater D. K. Olsen J. 0. Johnson R. A. Lillie T. A. Gabriel This report has been reproduced directly h m the best available copy. Available to DOE a…

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