A review of radionuclide behaviour in the primary system of a very-high-temperature reactor

Nuclear Engineering and Design

Volumn 239, Issue 12, 2009, Pages 3076-3091

  Kissane, M P ^a  

^a INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

Author keywords

[No Author keywords available]

Indexed keywords

ADSORPTION AND REACTIONS; ATOMIC IODINE; CARBONACEOUS DUST; CHEMICAL FORMS; DEPRESSURIZATIONS; DUST DEPOSITS; GASPHASE; HIGH-PURITY; IODINE CONCENTRATION; LOW CONCENTRATIONS; NORMAL OPERATIONS; NUCLEAR GRAPHITE; PEBBLE-BED; PRIMARY SYSTEMS; PRISMATIC DESIGN; QUANTITATIVE EVALUATION; RADIOLOGICAL RISKS; RADIONUCLIDE DISTRIBUTION; SAFETY EVALUATIONS; SYSTEM ENVIRONMENT;

ADSORPTION; ALLOYS; CESIUM; FISSION PRODUCTS; GAS TURBINES; GRAPHITE; HELIUM; HIGH TEMPERATURE REACTORS; INDUSTRIAL CHEMICALS; IODINE; KRYPTON; RADIOISOTOPES; RADIOLOGY; RADIOMETRY; RISK PERCEPTION; SILVER; SILVER ALLOYS; STRONTIUM; TRITIUM; XENON;

DUST;

EID: 70449632278     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.09.012     Document Type: Review

References (80)

1. ASTM, 2003. Standard terminology relating to manufactured carbon and graphite. ASTM C 709-03a.
2. ASTM, 2005. Standard specification for isotropic and near-isotropic nuclear graphite. ASTM D 7219-05.
3. Ball, S.J., Burchell, T.D., Corwin, W.R., Fisher, S.E., Forsberg, C.W., Morris, R.N., Moses, D.L., 2008. Next Generation Nuclear Plant GAP Analysis Report. ORNL/TM-2007/228.
4. Ball, S.J., Morris, R.N., 2008. Comprehensive survey of HTGR design and safety analysis tools for NGNP. ORNL/NRC/LTR-07/07, Oak Ridge National Laboratory.
5. Best J.V., Stephen W.J., and Wickham A.J. Radiolytic graphite oxidation. Progress in Nuclear Energy 16 2 (1985) 127-178
6. Bowsher B., Dickinson S., and Nichols A. Chemical interaction with primary circuit surfaces under severe accident conditions. Proceedings of the International Centre for Heat and Mass Transfer (1990) 415-432
7. Brenner K.G.E., and Graham L.W. Development and application of a unified corrosion model for a high-temperature gas-cooled reactor system. Nuclear Technology 66 2 (1984) 404-414
8. Burnette R.D., and Baldwin N.L. Primary Coolant Chemistry of the Peach Bottom and Fort St. Vrain High Temperature Gas-cooled Reactors. Specialists Meeting on Coolant Chemistry, Plate-Out and Decontamination in Gas-Cooled Reactors. Juelich, Germany, 2-4 Dec (1980) IAEA IWGGCR-2
9. Cabet C., Chapovaloff J., Rouillard F., Girardin G., Kaczorowski D., Wolski K., and Pijolat M. High temperature reactivity of two chromium-containing alloys in impure helium. Journal of Nuclear Materials 375 2 (2008) 173-184
10. Couturier R., and Escaravage C. High temperature alloys for the HTGR gas turbine: required properties and development needs. IAEA Technical Committee Meeting on Gas Turbine Power Conversion Systems for Modular HTGRs. 14-16 November 2000, Palo Alto, CA (USA), IAEA TECDOC-1238 (2000)
11. DOE, September 2007. Generation IV Nuclear Energy Systems - Ten-Year Program Plan - Fiscal Year 2007, vol. I. DOE Office of Nuclear Energy.
12. Elrick, R.M., Sallach, R.A., Ouellette, A.L., Douglas, S.C., 1984. Reaction between some cesium-iodine compounds and the reactor materials 304 stainless steel, Inconel 600 and silver, vol. I: Cesium hydroxide reactions. US NRC Report NUREG/CR-3197/1.
13. Engle, G.B., 1977. Assessment of grade H-451 graphite for replaceable fuel and reflector elements in HTGR. General Atomic Company Report GA-A14690.
14. Fachinger J., Koster A., Naicker L., Seubert M., Makumbe M., Caspary G., Kummer A.P., and Barnert H. Examination of dust in AVR pipe components. Proceedings of HTR 2008 (4th International Topical Meeting on High Temperature Reactor Technology). 28 September-1 October 2008, Washington DC, USA (2008)
15. Fontanet J., Herranz L.E., Ramlakan A., and Naicker L. PBMR confinement analysis during helium pressure boundary break. Proceedings of HTR 2008 (4th International Topical Meeting on High Temperature Reactor Technology). 28 September-1 October 2008, Washington, DC, USA (2008)
16. Forsyth, N., 1972. Tritium production and distribution in high temperature gas cooled reactors part 1: tritium production, migration and removal in the Dragon reactor between Core 5 charge III and Core 1 Charge IV. Dragon Project Report 799.
17. Forsyth, N., 1974. Tritium production and distribution in high temperature gas-cooled reactors: tritium generation, retention, distribution and environmental release in a notional 1500 MW(t) HTR. Dragon Project Report 905.
18. Fujikawa S., Hayashi H., Nakazawa T., Kawasaki K., Iyoku T., Nakagawa S., and Sakaba N. Achievement of reactor-outlet coolant temperature of 950 °C in HTTR. Journal of Nuclear Science and Technology 41 12 (2004) 1245-1254
19. Furrer D., and Fecht H. Ni-based superalloys for turbine discs. Journal of the Minerals, Metals and Materials Society 51 1 (1999) 14-17
20. Gainy, B.W., 1976. Review of tritium behavior in HTGR systems. General Atomic Co. GA-A-13461.
21. Gottaut H., and Krüger H. Results of experiments at the AVR reactor. Nuclear Engineering and Design 121 (1990) 143-153
22. Graham L.W. Corrosion of metallic materials in HTR-helium environments. Journal of Nuclear Materials 171 1 (1990) 76-83
23. Haas, H., 1984. Beschreibung RADAX 3. WER Report EA GHRA 001347.
24. Hanson D.L., Baldwin N.L., and Strong D.E. Fission Product Behaviour in the Peach Bottom and Fort St. Vrain HTGRs. Specialists meeting on coolant chemistry, plate-out and decontamination in gas-cooled reactors. Juelich, Germany, 2-4 Dec (1980) IAEA IWGGCR-2
25. Hinssen H.-K., Kühn K., Moormann R., Schlögl B., Fechter M., and Mitchell M. Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR. Nuclear Engineering and Design 238 11 (2008) 3018-3025
26. Hittner D., Bogusch E., Besson D., Buckthorpe D., Chauvet V., Fütterer M.A., van Heek A., Von Lensa W., Phélip M., Pirson J., Scheuermann W., and Verrier D. RAPHAEL, a European project for the development of HTR/VHTR technology for industrial process heat supply and cogeneration. Proceedings of HTR 2006 (3rd International Topical Meeting on High Temperature Reactor Technology). 1-4 October 2006, Johannesburg, South Africa (2006)
27. IAEA, 1997. Fuel Performance and Fission product Behaviour in Gas-cooled Reactors. IAEA-TECDOC-978.
28. IAEA, 2008. Accident Analysis for Nuclear Power Plants with Modular High Temperature Gas-cooled Reactors. IAEA Safety Reports series, no. 54.
29. Iniotakis N., Malinowski J., and Muenchow K. Initial results of investigations into fission product deposition in in-pile experiments. Nuclear Engineering and Design 34 (1975) 169-180
30. Katscher W., and Stauch B. Experimental investigation of aerosol formation from metallic fission products under hypothetical accident conditions in high-temperature gas-cooled reactors. Journal of Aerosol Science 20 8 (1989) 1417-1420
31. Katscher W., Moormann R., Verfondern K., v.d Decken C.B., Iniotakis N., and Hilpert K. Fission product behaviour and graphite corrosion under accident conditions in the HTR. Nuclear Engineering and Design 121 (1990) 219-225
32. Klueh R.L., and Nelson A.T. Ferritic/martensitic steels for next-generation reactors. Journal of Nuclear Materials 371 1-3 (2007) 37-52
33. Krueger K.J., and Ivens G.P. Safety-related experiences with the AVR reactor. Specialists Meeting on Safety and Accident Analysis for Gas-cooled Reactors. Oak Ridge, TN (USA), 13-15 May 1985, IAEA TECDOC-358 (1985)
34. Lafdi K., Bonnamy S., and Oberlin A. TEM studies of coal tars: crude tar and its insoluble fractions. Carbon 28 (1990) 57-63
35. Le Marois G., and Megnin M. Assessment of fission product deposits in the reactor coolant system: the DEVAP programme. Nuclear Safety 35 2 (July-December) (1994)
36. Luo X., Robin J.C., and Yu S. Comparison of oxidation behaviors of different grades of nuclear graphite. Nuclear Science and Engineering 151 (2005) 121-127
37. Luo X.-W., Yu S.-Y., Zhang Z.-S., and He S.-Y. Estimation of graphite dust quantity and size distribution of graphite particle in HTR-10. Hedongli Gongcheng/Nuclear Power Engineering 26 2 (2005) 203-208 (in Chinese)
38. McLaughlin B., Worsley M., Stainsby R., Grief A., Dennier A., MacIntosh S., and Van Heerden E. Heat transfer and tressure drop predictions for pebble bed HTGR cores. CSARP Meeting, 16-18 September 2008 (2008)
39. Minato K., Ogawa T., et al. Post-irradiation heating tests of ZrC coated fuel particles. Technical Committee Meeting on High Temperature Gas Cooled Reactor Technology Development. Johannesburg, South Africa. 13-15 Nov (1996) IAEA TECDOC-988
40. Moormann R., and Hilpert K. Chemical behavior of fission products in core heatup accidents in high-temperature gas-cooled reactors. Nuclear Technology 94 (1991) 56-67
41. Moormann R., Schenk W., and Verfondern K. Source term estimation for small-sized HTRs: status and further needs, extracted from German safety analyses. Nuclear Technology 135 (2001) 183-193
42. Moormann R., Hinssen H.-K., and Kühn K. Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphite. Nuclear Engineering and Design 227 3 (2004) 281-284
43. Moormann, R., 1992. Source term estimation for small sized HTRs. Report July-2669, Institut für Sicherheitsforschung und Reaktortechnik, FZ Jülich, Germany.
44. Moormann R. AVR experiments related to fission product transport. Proceedings HTR2006: 3rd International Topical Meeting on High Temperature Reactor Technology. 1-4 October 2006, Johannesburg, South Africa (2006)
45. Moormann, R., 2008. Fission product transport and source terms in HTRs: experience from AVR pebble bed reactor. Science and Technology of Nuclear Installations, vol. 2008, Article ID 597491, 14 pp.
46. Morris, R.N., Kissane, M., Petti, D., Powers, D., Wichner, R., 2008. Next generation nuclear plant phenomena identification and ranking tables (PIRTs): fission-product transport and dose PIRTs. US NRC, NUREG/CR-6944, vol. 3.
47. Muto Y., Ishiyama S., and Shiozawa S. Study of fission product release, plate-out and maintenance in helium turbomachinery. IAEA Technical Committee Meeting on Gas Turbine Power Conversion Systems for Modular HTGRs. Palo Alto, CA (USA), 14-16 Nov (2000) IAEA-TECDOC-1238
48. Nieder R. Predictions on an HTR coolant composition after operational experience with experimental reactors. Specialists meeting on coolant chemistry, plate-out and decontamination in gas-cooled reactors. Juelich, Germany, 2-4 Dec (1980) IAEA IWGGCR-2
49. Nieder R., and Sträter W. Long-term behavior of Impurities in an HTR primary circuit. VGB Kraftwerstechnik 68 7 (1988) 671-676
50. Nomura S., Fujii K., and Shindo M. Relation between gasification rates and gas desorption behavior with metallic impurities of carbon and graphite materials for the HTTR. Specialists Meeting on the Status of Graphite Development for Gas-cooled Reactors. Tokai, Ibaraki, Japan, 9-12 Sept (1991) IAEA TECDOC-6
51. NRC, August 2008. Next generation nuclear plant licensing strategy: a report to congress. www.ne.doe.gov/pdfFiles/NGNP_reporttoCongress.pdf.
52. Ohashi H., Sakaba N., Nishihara T., Tachibana Y., and Kunitomi K. Analysis of tritium behavior in very high temperature gas-cooled reactor coupled with thermochemical iodine-sulfur process for hydrogen production. Journal of Nuclear Science Technology 45 11 (2008) 1215-1227
53. Ohashi H., and Sherman S.R. Analytical study on tritium migration in NGNP and countermeasures to reduce tritium contamination. Transactions of the Atomic Energy Society of Japan 7 4 (2008) 439-451
54. Penning F.M. Über Ionisation durch metastabile Atome. Die Naturwissenschaften 15 (1927) 818
55. Peers, K., Grindon, E., Thompson, H., Verfondern, K., Garcia, M., Fontanet, J., Herranz, L.E., 2008. Report on available fission product plate-out data. RAPHAEL-2008-D-ST2.4.
56. Pop D., and Wolski K. Surface segregation in Haynes 230 alloy. Applied Surface Science 253 (2006) 2244-2250
57. Qiu X., He J., Guo G., Zuo K., and Zhang S. Development of the graphite matrix materials of the fuel elements for the 10MW HTR test module. Graphite Moderator Lifecycle Behaviour, Proceedings of a Specialists Meeting. Bath (UK), 24-27 September 1995, IAEA-TECDOC-901 (1996) (1995)
58. Quadakkers W.J., and Schuster H. Thermodynamic and kinetic aspects of the corrosion of high-temperature alloys in high-temperature gas-cooled reactor helium. Nuclear Technology 66 2 (1984) 383-391
59. Quadakkers W.J., and Schuster H. Corrosion of high-temperature alloys in the primary circuit helium of high temperature gas cooled reactors. Part I. Theoretical background. Werkstoffe und Korrosion 36 4 (1985) 141-150
60. Quadakkers W.J. Corrosion of high-temperature alloys in the primary circuit helium of high temperature gas cooled reactors. Part II. Experimental results. Werkstoffe und Korrosion 36 8 (1985) 335-347
61. Röllig K., Christ A., Haase F.W., and Wiedmann J. Caesium deposition on HTR primary circuit materials. Specialists Meeting on Fission Product Release and Transport in Gas-Cooled Reactors. Berkeley, UK, 22-25 Oct (1985) IWGGCR-13
62. Rouillard, F., 2007. Mécanismes de formation et de destruction de la couche d'oxyde sur un alliage chrominoformeur en milieu HTR. PhD thesis, Ecole Nationale Supérieure des Mines, Saint Etienne, France.
63. Rouillard F., Cabet C., Wolski K., Terlain A., Tabarant M., Pijolat M., and Valdivieso F. High temperature corrosion of a nickel base alloy by helium impurities. Journal of Nuclear Materials 362 (2007) 248-252
64. Sallach, R.A., Elrick, R.M., Douglas, S.C., Ouelette, A.L., 1986. Reactions between some cesium-iodide compounds and the reactor materials 304 stainless steel, Inconel 600 and silver, vol. II. Cesium iodide reactions. US NRC report NUREG/CR-3197/2 (SAND 83-0395).
65. Sawa K., Murata I., Saikusa A., Shindo R., Shiozawa S., and Baba O. Prediction of nongaseous fission products behavior in the primary cooling system of high temperature gas-cooled reactor. Journal of Nuclear Science Technology 31 7 (1994) 654-661
66. Sawa K., Shiozawa S., Kunitomi K., and Tanaka T. A study of silver behavior in gas-turbine high temperature gas-cooled reactor. Technical committee meeting on design and development of gas cooled reactors with closed cycle gas turbines. Beijing (China), 30 October-2 November 1995. IAEA TECDOC-899 (1995)
67. Shindo M., Quadakkers W.J., and Schuster H. Corrosion behaviour of high temperature alloys in impure helium environments. Journal of Nuclear Materials 140 2 (1986) 94-105
68. Skyrme G. Attachment of gaseous fission products to aerosols. Specialists Meeting on Fission Product Release and Transport in Gas-Cooled Reactors. Berkeley, UK, 22-25 Oct (1985) IWGGCR-13
69. Smith M.A., Frazier W.E., and Pregger B.A. Effect of sulfur on the cyclic oxidation behavior of a single crystalline, nickel-base superalloy. Materials Science and Engineering, A Structural Materials: Properties, Microstructure and Processing 203 (1995) 388-398
70. Stempniewicz M.M., Komen E.M.J., and de With A. Model of particle resuspension in turbulent flows. Nuclear Engineering and Design 238 11 (2008) 2943-2959
71. Strizak, J.P., Burchell, T.D., Windes, W.E., 2006. Status of initial assessment of physical and mechanical properties of graphite grades for NGNP applications. ORNL-GEN4/LTR-06-023.
72. Van der Merwe J.J. Development and validation of fission product release models and software at PBMR. 2nd International Topical Meeting on High Temperature Reactor Technology. Beijing, China, 22-24 September 2004 (2004)
73. Van Heek A.E., Siccama N.B., and Wakker P.H. Fission product transport in the primary system of a pebble bed high temperature reactor with direct cycle. IAEA Technical Committee Meeting on Gas Turbine Power Conversion Systems for Modular HTGRs. 14-16 November 2000, Palo Alto, CA (USA), IAEA TECDOC-1238 (2000)
74. Verfondern, K., Grindon, L., 2008. Fission product behavior in the graphite structures of the HTGR primary circuit. RAPHAEL Deliverable ST2.2.
75. Verfondern. K., 2009. Private communication.
76. Vreeling J.A., Wouters O., and Van der Laan J.G. Graphite irradiation testing for HTR technology at the High Flux Reactor in Petten. Journal of Nuclear Materials 381 (2008) 68-75
77. Wen K.Y., Marrow T.J., and Marsden B.J. The microstructure of nuclear graphite binders. Carbon 46 1 (2008) 62-71
78. Wichner, R.P., 1991. Fission product plateout and liftoff in the MHTGR primary system: a review. US NRC Report NUREG/CR-5647 (and ORNL/TM-11685).
79. Xerri B.J., Canneaux S., Cantrel L., Louis F., El Bakali A., and Pauwels J.F. Thermokinetic parameters calculation of {I-O-H} system in gas phase using theoretical chemistry. World Association of Theoretical and Computational Chemists (WATOC). Sydney (Australia), 14-19 September 2008 (2008)
80. 2 gases. Materials Science and Engineering A 477 (2008) 259-270