Accident consequences analysis of the HYLIFE-II inertial fusion energy power plant design

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Previous studies of the safety and environmental (S and E) aspects of the HYLIFE-II inertial fusion energy (IFE) power plant design have used simplistic assumptions in order to estimate radioactivity releases under accident conditions. Conservatisms associated with these traditional analyses can mask the actual behavior of the plant and have revealed the need for more accurate modeling and analysis of accident conditions and radioactivity mobilization mechanisms. In the present work a set of computer codes traditionally used for magnetic fusion safety analyses (CHEMCON, MELCOR) has been applied for simulating accident conditions in a simple model of the HYLIFE-II IFE design. ... continued below

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Reyes, S; Gomez del Rio, J & Sanz, J February 23, 2000.

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Previous studies of the safety and environmental (S and E) aspects of the HYLIFE-II inertial fusion energy (IFE) power plant design have used simplistic assumptions in order to estimate radioactivity releases under accident conditions. Conservatisms associated with these traditional analyses can mask the actual behavior of the plant and have revealed the need for more accurate modeling and analysis of accident conditions and radioactivity mobilization mechanisms. In the present work a set of computer codes traditionally used for magnetic fusion safety analyses (CHEMCON, MELCOR) has been applied for simulating accident conditions in a simple model of the HYLIFE-II IFE design. Here the authors consider a severe lost of coolant accident (LOCA) producing simultaneous failures of the beam tubes (providing a pathway for radioactivity release from the vacuum vessel towards the containment) and of the two barriers surrounding the chamber (inner shielding and containment building it self). Even though containment failure would be a very unlikely event it would be needed in order to produce significant off-site doses. CHEMCON code allows calculation of long-term temperature transients in fusion reactor first wall, blanket, and shield structures resulting from decay heating. MELCOR is used to simulate a wide range of physical phenomena including thermal-hydraulics, heat transfer, aerosol physics and fusion product release and transport. The results of these calculations show that the estimated off-site dose is less than 6 mSv (0.6 rem), which is well below the value of 10 mSv (1 rem) given by the DOE Fusion Safety Standards for protection of the public from exposure to radiation during off-normal conditions.

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175 Kilobytes pages

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  • 13th International Symposium on Heavy Ion Inertial Fusion, San Diego, CA (US), 03/13/2000--03/17/2000

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  • Report No.: UCRL-JC-136106
  • Report No.: AT6010400
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 756839
  • Archival Resource Key: ark:/67531/metadc711056

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  • February 23, 2000

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  • Sept. 12, 2015, 6:31 a.m.

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  • May 5, 2016, 9 p.m.

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Reyes, S; Gomez del Rio, J & Sanz, J. Accident consequences analysis of the HYLIFE-II inertial fusion energy power plant design, article, February 23, 2000; California. (digital.library.unt.edu/ark:/67531/metadc711056/: accessed July 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.