Safety assessment of two advanced ferritic steel molten salt blanket design concepts

Fusion Engineering and Design

Volumn 72, Issue 1-3 SPEC. ISS., 2004, Pages 277-306

  Merrill, B J ^a   Sawan, M ^b   Wong, C P C ^c   Nygren, R E ^d   Cadwallader, L C ^a   Malang, S ^e   Sze, D K ^f  

^a IDAHO NATIONAL LABORATORY   (United States)

^b UNIVERSITY OF WISCONSIN MADISON   (United States)

^c GENERAL ATOMICS   (United States)

^d SANDIA NATIONAL LABORATORIES   (United States)

^e Fusion Nuclear Technology Consulting   (Germany)

^f UNIVERSITY OF CALIFORNIA   (United States)

Author keywords

APEX; Bypass accidents; Fusion safety; LOCA; LOVA; Molten salts; Site dose

Indexed keywords

FERRITE; FUSION REACTIONS; HEAT FLUX; PLASMA HEATING; SALTS; STEEL; THERMAL EFFECTS;

FERRITIC STEELS; LIQUID SURFACES; MOLTEN SALTS; SAFETY ASSESSMENT;

MOLTEN MATERIALS;

EID: 7444252346     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2004.07.010     Document Type: Article

References (67)

1. M.A. Abdou, The APEX Team, On the exploration of innovative concepts for fusion chamber technology, Fus. Eng. Des. 54 (2000) 181.
2. C.P.C. Wong, The APEX Team, Advanced ferritic steel, FliBecooled first wall and blanket design, Fus. Eng. Des. (2003).
3. R.E. Nygren, The APEX Team, A fusion reactor design with a liquid first wall and divertor, Fus. Eng. Des. (2003).
4. Steve Zinkle, et al., Microstructure and mechanical properties of oxide dispersion-strengthened steels, DOE Fusion Materials Semiannual Progress Report for the period ending, 30 June 2000, pp. 123-130 (DOE/ER-0313/28).
5. Technical Basis for the ITER Final Design Report, Cost Review and Safety Analysis (FDR), ITER EDA Documentation Series No. 16, International Atomic Energy Agency, Vienna, 1998, pp. 36-50 (Chapter IV).
6. DOE STD 6002-96, The safety of magnetic fusion facilities: requirements, May 1996.
7. M.L. Abbott, L.C. Cadwallader, D.A. Petti, Radiological dose calculations for fusion facilities, INEEL Report, INEEL/EXT-03-00405, April 2003.
8. M.A. Tillack, et al., Engineering design of the ARIES-RS power plant, Fus. Eng. Des. 41 (1998) 491.
9. R.E. Alcouffe et al., DANTSYS 3.0, One-, two-, and three-dimensional multigroup discrete ordinales transport code system, RSICC computer code collection CCC-547, Contributed by Los Alamos National Lab, August 1995.
10. M.J. Sisolak, Q. Wang, H. Khater, D. Henderson, DKR-PULSAR2.0: a radioactivity calculation code that includes pulsed/intermittent operation, University of Wisconsin Fusion Technology Institute Report UWFDM-1250, 2004.
11. A. Pashchenko et al., FENDL/A-2.0: Neutron activation cross-section data library for fusion applications, Report INDC(NDS)-173, IAEA Nuclear Data Section, March 1997.
12. Nuclear Regulatory Commission, 10CFR part 61, Licensing requirements for land disposal of radioactive waste, Federal Register, FR 47, 57446, 1982.
13. S. Fetter, E. Cheng, F. Mann, Long term radioactive waste from fusion reactors, Fus. Eng. Des. 13 (1990) 239-246.
14. R. Kluch, E. Cheng, M. Grossbeck, E. Bloom, Impurity effects on reduced activation ferritic steels developed for fusion applications, J. Nucl. Mater. 280 (2000) 353-359.
15. L. Berardinucci, M. Dalle Donne, Tritium control in the European helium cooled pebble bed blanket, Fusion Technology 1996, in: Proceedings of the 19th Symposium on Fusion Technology, Elsevier Publishers, Amsterdam, 1997, p. 1427.
16. B.J. Merrill, J.L. Jones, D.F. Holland, TMAP/MOD1: tritium migration analysis program code description and user's manual, Idaho National Engineering Laboratory Report, EGG-EP-7407, April 1988.
17. M.I. Baskes, A calculation of the surface recombination rate constant for hydrogen isotopes on metals, J. Nucl. Mater. 92 (1980) 318.
18. M.A. Pick, K. Sonnenberg, A model for atomic hydrogen-metal interactions, J. Nucl. Mater. 131 (1985) 208.
19. O.V. Ogorodnikiva, et al., Tritium permeation through the first wall of the EU-HCPB blanket, Fus. Eng. Des. 49-50 (2000) 921.
20. E. Serra, A. Perujo, Influence of the surface condition on the permeation in the deuterium-MANET system, J. Nucl. Mater. 240 (1997) 215.
21. L.A. Sedano, et al., The deuterium recombination and dislocation constants for MANET derived from plasma implantation experiments, JRC Euroreport EUR 17713 EN, 1997.
22. E. Serra, Influence of traps on the deuterium behavior in low activation martensitc steels F82H and Batman, J. Nncl. Mater. 245 (1997) 108.
23. G.R. Longhuist, Permeation of tritium through HYLIFE-II heat exchanger tubes, Idaho National Engineering Laboratory Report EGG-FSP-8678, September 1989.
24. G.R. Longhurst, T.J. Dolan, HYLIFE-II tritium management system, Idaho National Engineering Laboratory Report, EGG-FSP-9971, June 1993.
25. H. Katsuta, K. Farukawa, Diffusivity and solubility of hydrogen in molten fluoride mixtnre (LiF-NaF-KF), J. Nucl. Mater. 71 (1978) 375.
26. A.P. Malinauskas, D.M. Richardson, The solubilities of hydrogen, deuterium, and helium in molten Li2BeF4, Ind. Eng. Chem. Fundam. 13 (1974) 242.
27. H.F. Andersen, et al., Guide to good practices at DOE tritium facilities, Mound Laboratory Report MLM-3610, October 1989, pp. 3-15/27.
28. P. Norajitra, et al., Conceptual design of the dual-coolant blanket in the frame of the EU power plant conceptual study, Forschungszentrum Karlsruhe Report FZKA 6780, November 2002. p. 42.
29. US Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants, Subpart H, National Emission Standards for Emissions of Radionuclides Other Than Radon from Department of Energy Facilities, Section 92, Standard, US Government Printing Office, Washington DC, 13 November 2002.
30. L. Cadwallader, D. Petti, Safety in the design of three burning plasma experiments. Fus. Sci. Technol. 44 (2003) 38-392.
31. US Code of Federal Regulations, Title 40, Protection of the Environment, Part 141, National Primary Drinking Water Regulations, Subpart B, Maximum Contaminant Levels, Section 16, Maximum contaminant levels for beta particle and photon radioactivity from man-made radionnclides in community water systems, US Government Printing Office, Washington, DC, 26 November 2002.
32. K.Y. Wong. et al., Canadian tritium experience, Canadian Fusion Fuels Technology Project, Ontario Hydro Report, 1984.
33. M.C. Billone, C.C. Lee, D.L. Balwin, Tritium and helium behavior in irradiated beryllium, Fus. Technol. 19 (1991) 1707.
34. D.L. Baldwin, M.C. Billone, Diffusion/desorption of tritium from irradiated beryllium, J. Nucl. Mater. 212-215 (1994) 948.
35. D.V. Andreev, et al., Post-irradiation studies of beryllium reflectors of fission reactor, examination of gas release, swelling and structure of beryllium under annealing, J. Nucl. Mater. 244-237 (1996) 880.
36. D.K. Craig, et al., Alternative Guideline Limits for Chemicals without ERPGs, Am. Ind. Hyg. Assoc. J. 56 (1995) 919-925.
37. D.E. Craig et al., ERPGs and TEELs for chemicals of concern, Westinghouse Safety Management Solutions LLC, Aiken, SC, WSMS-SAE-02-0171, Revision 19, 6 December 2002, Available at the web site http://tis.eh.doe.gov/web/chem_safety/.
38. L.C. Cadwallader, Chemical hazards and safety issues in fusion safety design. Fus. Sci. Technol. 44 (2003) 369-374.
39. Toxicological review of beryllium and compounds, EPA/635/R-98/008, US Environmental Protection Agency, April 1998.
40. Evaluation, of the potential carcionogenicity of beryllium, beryllium chloride, beryllium fluoride, and beryllium nitrate, Syracuse Research Corporation, Syracuse, New York EPA/600/8-91/078, Jnne 1988.
41. G.L. Finch, et al., Animal models of beryllium-induced lung disease, Env. Health Pers. 104 (1996) 973-979.
42. Tenth Report on Carcinogens, National Toxicology Program, US Department of Health and Human Services, Washington DC, 2002.
43. Toxicological profile for fluorides, hydrogen fluoride, and fluorine, ATSDR-TP-11, Agency for Toxic Substances and Disease Registry, US Public Health Service, September 2003 (Section 2.2.1).
44. E.J. Largent, Fluorosis, the Health Aspects of Fluorine Compounds, Ohio State University Press, Columbus, Ohio, 1961.
45. R.O. Gauntt, et al., MELCOR Computer Code Reference Manuals: Version 1.8.4, NUREG/CR-6619, vol. 2, Rev. 1, July 1997, pp. HS-RM 37-41.
46. B.J. Merrill, R.L. Moore, S.T. Polkinghome, D.A. Petti, Modifications to the MELCOR code for application in fusion accident analysis, Fus. Eng. Des. 51-52 (2000) 555-563.
47. R-L. Moore, Flibe thermal properties for use with the fusion safety multi-fluid equation of state package, Idaho National Engineering and Environmental Laboratory Report, INEEL/EXT-2000-00670, May 2000.
48. R. AYMAR, et al., Technical basis for the HER final design report, cost reviews and safety analysis (FDR), ITER Design Team Document, S CA LS 3997-12-19 F1, December 1997, pp. 4.3-5.
49. C.P.C. Wong, et al., Evaluation of the tungsten alloy vaporizing lithium first wall and blanket concept, Fus. Technol. 39 (2001) 815-822.
50. R. Aymar, et al., ITER-FEAT Plant description document, ITER Design Team Document, GA0FDR 101-07-13R1.0, July 2001, p. 9 (Chapter 2.2).
51. R.O.A- Hall, D.G. Martin, The thermal conductivity of powder beds, J. Nucl. Mater. 101 (1981) 172.
52. R.B. Bird, W.E. Stewart, E.N. Lightfoot, Transport Phenomena, Wiley, New York, 1960 (Chapter 8).
53. H.-W. Bartels (Ed.), Accident Analysis Specifications for NSSR-2 (AAS), Version 2, ITER Safety Team Report, S 81 RI 1997-05-04 W1.1, SEHD 8.1.C-1, 6 May 1997.
54. Y.S. Touloukian, Thermophysical Properties of High Temperature Solid Materials, MacMillian, New York, 1967.
55. K.A. McCarthy, G.R. Smolik, S.L. Harms, A summary and assessment of oxidation driven volatility experiments at the INEL and their application to fusion reactor safety assessments, Idaho National Engineering and Environmental Laboratory Report, EGG-FSP-11193, September 1994.
56. J.G. Collier, J.R. Thome, Convective Boiling and Condensation, third ed., Claredon Press, Oxford, 1994.
57. J.M. Smith, H.C. Van Ness, Introduction to Chemical Engineering Thermodynamics, McGraw-Hill, New York, 1959.
58. 2/LiF(FLIBE) molten mixtures, Fus. Sci. Technol. 41 (2002) 141-150.
59. B.J. Merrill, Preliminary Flinak mobilization measurements and implications for Flinabe safety, Presentation at 2nd APEX Physical Meeting for FY2001, http://www.fusion.ucla.edu/APEX/, 9 November 2001.
60. R.C. Reid, J.M. Prausnitz, B.E. Poling, The Properties of Gases and Liquids, fourth ed., McGraw-Hill, New York, 1987.
61. J.P. Holman, Heat Transfer, fifth ed., McGraw-Hill, Inc, New York, 1981.
62. S.K. Friedlander, Smoke, dust and haze, Wiley, New York, 1977.
63. Ibid., p. 240.
64. M.L. Abbott, L.C. Cadwallader, D.A. Petti, Radiological dose calculations for fusion facilities, INEEL Report, INEEL/EXT-03-00405, April 2003.
65. S. Malang, T. Mattas, Comparison of lithium and eutectic lead-lithium alloy, two candidate liquid metal breeder materials of self-cooled blankets, Fus. Eng. Des. 27 (1995) 399-406.
66. Guidelines for Chemical Process Quantitative Risk Analysis, second ed., American Institute of Chemical Engineers, New York, 2000, pp. 111-125.
67. R. Hultgren, et al., Selected Values of the Thermodynamic Properties of the Elements, American Society for Metals, Metals Park, Ohio, 1973.