Thermal-hydraulic development a small, simplified, proliferation-resistant reactor.

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This paper addresses thermal-hydraulics related criteria and preliminary concepts for a small (300 MWt), proliferation-resistant, liquid-metal-cooled reactor system. A main objective is to assess what extent of simplification is achievable in the concepts with the primary purpose of regaining economic competitiveness. The approach investigated features lead-bismuth eutectic (LBE) and a low power density core for ultra-long core lifetime (goal 15 years) with cartridge core replacement at end of life. This potentially introduces extensive simplifications resulting in capital cost and operating cost savings including: (1) compact, modular, pool-type configuration for factory fabrication, (2) 100+% natural circulation heat transport with the possibility ... continued below

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29 p.

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Farmer, M. T.; Hill, D. J.; Sienicki, J. J.; Spencer, B. W. & Wade, D. C. July 2, 1999.

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Description

This paper addresses thermal-hydraulics related criteria and preliminary concepts for a small (300 MWt), proliferation-resistant, liquid-metal-cooled reactor system. A main objective is to assess what extent of simplification is achievable in the concepts with the primary purpose of regaining economic competitiveness. The approach investigated features lead-bismuth eutectic (LBE) and a low power density core for ultra-long core lifetime (goal 15 years) with cartridge core replacement at end of life. This potentially introduces extensive simplifications resulting in capital cost and operating cost savings including: (1) compact, modular, pool-type configuration for factory fabrication, (2) 100+% natural circulation heat transport with the possibility of eliminating the main coolant pumps, (3) steam generator modules immersed directly in the primary coolant pool for elimination of the intermediate heat transport system, and (4) elimination of on-site fuel handling and storage provisions including rotating plug. Stage 1 natural circulation model and results are presented. Results suggest that 100+% natural circulation heat transport is readily achievable using LBE coolant and the long-life cartridge core approach; moreover, it is achievable in a compact pool configuration considerably smaller than PRISM A (for overland transportability) and with peak cladding temperature within the existing database range for ferritic steel with oxide layer surface passivation. Stage 2 analysis follows iteration with core designers. Other thermal hydraulic investigations are underway addressing passive, auxiliary heat removal by air cooling of the reactor vessel and the effects of steam generator tube rupture.

Physical Description

29 p.

Notes

INIS; OSTI as DE00011745

Medium: P; Size: 29 pages

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  • 10th Annual Engineering and Science Conference, Obninsk (RU), 06/28/1999--07/02/1999

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  • Report No.: ANL/RE/CP-98725
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11745
  • Archival Resource Key: ark:/67531/metadc621194

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • July 2, 1999

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  • June 16, 2015, 7:43 a.m.

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  • April 10, 2017, 7:09 p.m.

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Farmer, M. T.; Hill, D. J.; Sienicki, J. J.; Spencer, B. W. & Wade, D. C. Thermal-hydraulic development a small, simplified, proliferation-resistant reactor., article, July 2, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc621194/: accessed April 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.