5
Views
4
CrossRef citations to date
0
Altmetric
Technical Paper

Simulation of Cleanup of Tritiated Water in Fusion Reactor-Size Concrete Enclosures

, &
Pages 466-472 | Published online: 10 Aug 2017

References

  • J. L. ANDERSON and R. H. SHERMAN, “Tritium Systems Test Assembly,” LA-6855-P, Los Alamos National Laboratory (1977).
  • A. E. SHERWOOD, “Dynamic Model of Tritium Cleanup in an Enclosure with Wall Diffusion,” UCRL-80572, Lawrence Livermore National Laboratory (1978).
  • R. G. CLEMMER et al., “Simulation of Large Scale Air Detritiation Operation by Computer Modeling and Bench-Scale Experimentation,” ANL/FPP/77-3, Argonne National Laboratory (1977).
  • S. TANAKA et al., “Simulation of Soaking Effect in Air Detritiation System,” Fusion Eng. Des., 7, 353 (1989).
  • R. H. LAND et al., “TSOAK-Ml: A Computer Code to Determine Tritium Reaction/Adsorption/Release Parameters from Experimental Results of Air-Detritiation Tests,” ANL-79-82, Argonne National Laboratory (1980).
  • J. S. WATSON et al., “Environmental Effects of Fusion Power Plants. Part II: Tritium Effluents,” Fusion Technol., 12, 354 (1987).
  • G. CASINI et al., “Environmental Aspects of Fusion Reactors 1985,” EUR-10728-EN, Commission of the European Communities (1986).
  • R. A. JALBERT et al., “Contamination of Aluminum and Painted Surfaces Exposed to Tritium,” Fusion Technol., 10, 1223 (1986).
  • S. NUMATA et al., “Diffusion of Tritiated Water Vapor into Concrete,” Fusion Technol., 19, 140 (1991).
  • S. NUMATA et al., “Diffusion of Tritiated Water in Cement Materials,” J. Nucl. Mater., 171, 2 &3, 373 (1990).
  • A. E. SHERWOOD, “Tritium Accident Containment Within a Large Fusion Enclosure: Cost, Benefit, and Risk Considerations,” UCRL Preprint-88932, Lawrence Livermore National Laboratory (1983).
  • H. J. REILLY et al., “Tritium Safety Issues for TFCX,” EGG-M-20684, EG&G Idaho, Inc. (1985).
  • “International Tokamak Reactor, Phase Two A, Part I,” International Atomic Energy Agency (1983).
  • “Annual Report of the Fusion Research and Development Center for the Period of April 1, 1979 to March 31, 1980,” JAERI-M 9421, Japan Atomic Energy Research Institute (1981).
  • S. Z. BRUSKE and D. F. HOLLAND, “Risk Assessment of a Fusion Reactor Fuel Processing System,” EGG-2266, EG&G Idaho, Inc. (1983).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.