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Abstract

Conditions of plant operation like availabilities, load conditions, or aspects related to the fuel and fuel cycle are explained. Radiation exposures during operation are compared to those which are existing in any case for the population, and it is shown that nuclear power plants contribute to a very small share to the total values (e.g., less than 0.5% in Germany). Related to the time-dependent evaluation of operation of nuclear reactors, one has to distinct between long-term effects (burnup of fuel), midterm effects (e.g., Xenon effects), and short-term effects (accidents). The burnup of fuel is a suited measure to calculate the release of energy from the fuel elements. In HTR fuel burnup values of more than 100,000 MWd/t can be realized without any difficulty because of the use of coated particles. During the reactor operation higher isotopes like Plutonium and minor actinides are formed. Partly they are fissioned already during operation. The rest, contained in spent fuel elements, has a large importance for the evaluation of process of direct final storage of spent fuel elements. The fission product inventory, formed during operation, and the radioactivity of the isotopes forms the most important question of reactor safety. The retention of fission products in the coated particle fuel is very effective, as well during reactor operation, during accidents, and in the steps of waste management. The system of dynamical equations, which is given in this chapter in simplified form for the core and for the whole plant, allows a description of the processes of operation and control of the chain reaction. Simplified solutions shall explain important topics like changes of temperatures and isotopes in the reactor. Mainly, the isotopes Xenon and Samarium need special attention in the connection. The Xenon dynamic requires special additional contributions in the control system, and even oscillations of neutron fluxed can be caused by changes of this strongly absorbing fission product. Multi-dimensional computer programs today are applied to cover all these effects mentioned before. The decay heat removal in normal operation is carried out by production loops or auxiliary loops. In case of failure of these systems, the self-acting decay heat removal takes place. This is one of the important safety aspects of modular HTR. The inert thermal behavior of the core, caused by small power density and large mass of graphite, is one of the preconditions to realize the special safety characteristics. Some numbers on release rates of radioactivity during operation are given, and it is indicated that the dose rate applied to personal is relatively small in HTR plants. The different processes of waste management are explained in a short overview. They are based on the developed methods applied in today introduced reactors.

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References

  1. Friedrich K., Weicht U., Concept of control and load following of the THTR-300 power plant Uentrop, VGB-Kraftwerkstechnik, Heft 5, 1977

    Google Scholar 

  2. Ziermann E., Ivens G., Final report on the power operation of the AVR experimental nuclear power plant, JÜL-3448, 1997

    Google Scholar 

  3. Hansen U., Study for the load following of THTR-300 MW prototype power plant, JÜL-571-RG, 1969

    Google Scholar 

  4. Bodansky D., Nuclear energy – principles, practices and prospects, Springer Verlag, 2004

    Google Scholar 

  5. Herrmann A. G., Radioactive waste – problems and responsibility, Springer Verlag, Berlin, Heidelberg, New York, 1983

    Google Scholar 

  6. Bäumer R. and Kalinowski I., THTR commissioning and operating experience, 11th International Conference on the HTGR, Dimitrorgrad, June 1989

    Google Scholar 

  7. Massimo L., Physics of high-temperature reactors, Verlag Pergamon Press, Oxford, 1976

    Google Scholar 

  8. Teuchert E., Fuel cycles of pebble-bed high-temperature reactors in the computer simulation, JÜL-2069, 1986

    Google Scholar 

  9. Leushacke D. F. and Kaiser G. G., The HTR fuel cycle program on the Federal Republic of Germany, ENC 79, Trans. Am. Nucl. Soc. 31, 1979

    Google Scholar 

  10. Teuchert E., Hansen U. and Haas K. A., VSOP – Computer code system for reactor and fuel cycle simulation, JÜL-1649, March 1980

    Google Scholar 

  11. Teuchert E., Rütten H. J. and Werner H., Reducing the world uranium requirement by the thorium fuel cycle in high-temperature reactors, Nuclear Technology 58, Sept. 1982

    Google Scholar 

  12. IAEA, Potential of thorium based fuel cycles to constrain plutonium and reduce long-lived waste toxicity, Final Report of a Coordinated Research Project, IAEA TECDOC-1349, Apr. 2003

    Google Scholar 

  13. INFCE, International evaluation of nuclear fuel cycles, summarizing overview, INFCE Summary Volume, IAEA, Vienna, 1980

    Google Scholar 

  14. Trauger D. B., Thorium utilization, Annals of Nuclear Energy, vol. 5, 1978

    Article  Google Scholar 

  15. Teuchert E., Berger-Rossa R., Haas K. A., Rütten K. J., Wolf L. and Wuttke G., Physics of the HTR for process heat, Nuclear Engineering and Design, 78, 1984

    Article  Google Scholar 

  16. Emendörfer D. and Höcker K. H., Theories of nuclear reactors – the instationary reactor, Vol. 2, BI Wissenchafsverlag, Mannheim, 1993

    Google Scholar 

  17. Schrüfer E. (edit.), Radiation and radiation measurement in nuclear power plants, Elitera-Verlag, Berlin, 1974

    Google Scholar 

  18. Benedict M., Pigfort T. H. and Levi H. W., Nuclear chemical engineering, McGraw Hill Book Company, New York, 1981

    Google Scholar 

  19. Merz E. and Walter E., Advanced nuclear systems consuming excess plutonium, Kluwer Academic Publishers, Dordrecht/Boston/London, 1997

    Google Scholar 

  20. AN, Reactor physics constants, Argonne National Laboratory, ANL-5800, United States Atomic Energy Commission, 1963

    Google Scholar 

  21. Ziegler A., Source book on reactor technology, Vol. 1–3, Springer Verlag, Berlin, Heidelberg, New York, Tokyo, 1983

    Google Scholar 

  22. Etherington E., Nuclear Engineering Handbook, McGraw Hill Book comp., Inc., New York, 1958

    Google Scholar 

  23. Browne E., Firestone R. B. and Shirley V. S., Table of radioactive isotopes Wiley, New York, 1986

    Google Scholar 

  24. Niephaus D., Reference concept for the direct final storage of spent HTR fuel elements in CASTOR THTR/AVR transport and storage vessels, JÜL-3734, 1999

    Google Scholar 

  25. NN, Nuclear technology – facts, data, number, Inforum, Kerntechnische Gesellschaft, 1989

    Google Scholar 

  26. Schultz M. A., Control of nuclear reactors and power plants, 2nd ed., McGraw Hill, 1961

    Google Scholar 

  27. Profos P., The control of steam plants, Springer Verlag, 1962

    Google Scholar 

  28. Harrer J. M., Nuclear reactor control engineering, D. van Nostrand Comp. Princeton, 1963

    Google Scholar 

  29. Keepin G. R., Physics of nuclear kinetics, Adison Wesley Publishing Comp. Inc., Reading, 1965

    Google Scholar 

  30. Weaver L. E., Reactor dynamics and control, American Elsevier Publishing Comp. Inc. New York, 1968

    Google Scholar 

  31. Hetrick D. L., Dynamics of nuclear systems, The University of Arizona Press, Tuscon, 1972

    Google Scholar 

  32. Lamarsh J. R., Introduction to nuclear reactor theory, Addison Wesley Publishing Company, Reading, 1972

    Google Scholar 

  33. Gerwin H., The two dimensional reactor dynamic program TINTE, part I: JÜL-2167, Nov. 1987, part II: JÜL-2266, Feb. 1989

    Google Scholar 

  34. Thomas F., HTR 2000: Program code for calculation of operation of HTR, JÜL-2261, Jan. 1989

    Google Scholar 

  35. Teuchert E., Fuel cycles of the pebble-bed high-temperature reactor in the computer simulation, JÜL-2069, 1986

    Google Scholar 

  36. Teuchert E., Bohl L., Rütten H. J. and Haas K. A., The pebble-bed high-temperature reactor as a source of nuclear process heat, Core Physics Studies, Vol. 2, JÜL-1114-RG, 1974

    Google Scholar 

  37. Rütten H. J., Haas K. A., Brockmann H. and Scherer W., VSOP (99/05) computer code system, JÜL-4189, Oct. 2005

    Google Scholar 

  38. Biesenbach R., Analysis of the instationary behavior of a controlled HTR-Module power plant, Diss. RWTH Aachen, 1995

    Google Scholar 

  39. Scharf H. J. and Vigassy J., DYNOTTO, an axial one-dimensional program for the analysis of spatial and time dependence of high-temperature reactor with pebble-bed fuel elements, JÜL-1246, Oct. 1975

    Google Scholar 

  40. Schultes K. H., Analysis of temperature coefficient and of short-time dynamics of pebble-bed reactor PNP 3000, Diss. RWTH Aachen, 1978

    Google Scholar 

  41. INTERATOM/KRAFTWERKSUNION, Siemens High temperature reactor – Module powerplant, Plant – and Safety concept Vol 1,2, 1984

    Google Scholar 

  42. Banaschek J., Calculation methods and analysis for the dynamic behavior of power plants with high-temperature reactors, JÜL-1841, 1983

    Google Scholar 

  43. Scherer W., Gerwin H., Kindt T. and Patscher W., Analysis of reactivity and temperature transient experiments at the AVR high-temperature reactor, Nucl. Sci. Eng. 97, 1987

    Article  Google Scholar 

  44. Ash M., Nuclear reactor kinetics, McGaw Hill Company, New York, 1965

    Google Scholar 

  45. Scharf H. J., Analysis of short-time dynamics of OTTO pebble-bed reactors, JÜL-1169, 1975

    Google Scholar 

  46. Heckhoff H. D., Analysis of disturbance of operation without shutdown (ATWS accidents) in high-temperature reactors, JÜL-1743, 1981

    Google Scholar 

  47. Engelbrecht H., Analysis on the dynamics of pebble-bed high-temperature reactors, JÜL-Spez, 123, 1981

    Google Scholar 

  48. Grotkamp T., Establishing a three-dimensional simulation program for describing the core physics of pebble-bed reactors with several passages on the example of AVR, JÜL-1888, 1984

    Google Scholar 

  49. Elsheakh A. F., Simulation program for the THTR 300 to calculate transients in case of emergency cooling, JÜL-2368, 1990

    Google Scholar 

  50. Hoffmann J., Simulation of the plant behavior of THTR 300 using measured data during the period of start of operation, JÜL-2359, 1990

    Google Scholar 

  51. Mulder E. J., Pebble-bed reactor with equalized core power distribution – inherently safe and simple, JÜL-2632, 1999

    Google Scholar 

  52. Lamarsh J. R., Introduction to nuclear reactor theory, Addison Wesley Publishing Company Reading, Menlo Parks, London, Amsterdam, Don Mills, Sidney, 1972

    Google Scholar 

  53. Bäumer R., THTR 300 – experiences with a progressive technology, Atomwirtschaft, May 1989

    Google Scholar 

  54. Lauer A., Design of a concept to control the power and to govern Xenon oscillations in HTR-K 3000 and PNP 3000, JÜL-1446, 1977

    Google Scholar 

  55. Rydin R.A., Nuclear reactor theory and design, PBS Series in Reactor Physics, Blacksburg, 1977

    Google Scholar 

  56. Mertens J., Analysis of control of power and governing of Xenon oscillations in pebble-bed high-temperature reactor PNP 3000, JÜL-Spez-127, 1981

    Google Scholar 

  57. Kirch N. and Ivens G., Results of AVR experiments in: AVR – Experimental High-Temperature Reactor, VDI-Verlag, Düsseldorf, 1990

    Google Scholar 

  58. Lukaszewicz J., Temperature behavior of a high-temperature reactor after total loss of cooling, JÜL-1112-RG, 1974

    Google Scholar 

  59. Singh J., Analysis of the thermodynamic transients in the core of a high-temperature reactor, JÜL-937-RG, 1973

    Google Scholar 

  60. Rehm W., Analysis of the delayed decay heat removal in a pebble-bed high-temperature reactor concept with large power as a contribution to the possibilities of limitation of hypothetical accidents, JÜL-1645, 1980

    Google Scholar 

  61. Petersen K., Safety concept of high-temperature reactors with natural removal of heat from the core in accidents, JÜL-1872, 1983

    Google Scholar 

  62. Wachholz W., Safety concept of future nuclear power plants HTR 500 and HTR 100, Atomkernenergie-Kerntechnik, Vol. 47, No. 3, 1985

    Google Scholar 

  63. Reutler H. and Lohnert G. H., The modular HTR – a new concept for the pebble-bed reactor, Atomwirtschaft, 27, Jan. 1982

    Google Scholar 

  64. Kugeler K., The decay heat removal as a key question of reactor safety, Wissenschaft und Umwelt, 1, 1993

    Google Scholar 

  65. Ziermann E. and Ivens G., Final report on the power generation of the AVR experimental nuclear power plant, JÜL-3448, Oct. 1997

    Google Scholar 

  66. Bäumer R. and Kalinowski I., THTR – commissioning and operating experiences, 11th International Conference on the HTGR, Dimitrogra, June 1989

    Google Scholar 

  67. Von der Decken C. B., Wawrzik, Dust and activity behavior, in: AVR Experimental High-Temperature Reactor, VDI-Verlag, Düsseldorf, 1990

    Google Scholar 

  68. Krawczynski S. J. B., radioactive waste – processing, storage and disposal, Thiemig Verlag, München, 1967

    Google Scholar 

  69. NN, Modern power station practice, Vol. J, Nuclear Power Generation, Pergamon Press, Oxford, New York, Seoul, Tokyo, 1992

    Google Scholar 

  70. Baumgärtner (edit), Chemistry of nuclear waste management, 3 volumes, Verlag Karl Thiemig, München, 1980

    Google Scholar 

  71. A. Ziegler, Reactor technology, Vol 3 Springer Verlag, Berlin, Heidelberg, New York, Tokyo.

    Google Scholar 

  72. Kautz J. A., Chemical engineering for nuclear power plant in: Oldekopp W. (edit.), Pressurized Water Reactors for Nuclear Power Plants, Verlag Karl Thiemig, München, 1974

    Google Scholar 

  73. Bohn Th. (edit.), Nuclear power plants, Vol. 10 of Handbook of Energy, Technischer VerlagResch, Verlag TÜV Rheinland, 1986

    Google Scholar 

  74. Röllig K. et al., Waste management for high-temperature reactors, JÜL-Conf-61, 1987

    Google Scholar 

  75. Dietrich G. et al., Decommissioning of thorium high-temperature reactor (THTR-300), IAEA-TECDOC 1043, Vienna, 1998

    Google Scholar 

  76. Bäumer R., THTR 300 – experiences with progressive technology, Atomwirtschaft, May 1989

    Google Scholar 

  77. Fachinger J. et al., R + D on intermediated storage and final disposal of spent HTR fuel, IAEA-TECDOC-1043, Vienna, 1998

    Google Scholar 

  78. Kirch N., Briukmann H.U., Brücher P.H., Storage and final disposal of spent HTR fuel in the Federal Republic of Germany, Nuclear Engineering and Design, 121, 1990

    Article  Google Scholar 

  79. Bäumer R., The situation of THTR in October 1989, VGB KraftwerksTechnik, 1, 1990

    Google Scholar 

  80. Vollrath J., Documentation of the shutdown of the THTR 300, Hochtemperatur Kern Kraft GmbH, Hamm Kentrop, Sept. 1997

    Google Scholar 

  81. Niephaus D., Barnert E., Brücher P.H., Kroth K., Final disposal of dissolver sludges, claddings, fuel hardware, and spent HTGR fuel elements in the Federal Republic of Germany, Proc. 1989 Joint Int. Waste Management Conf., Kyoto, 1989

    Google Scholar 

  82. IAEAFuel performance and fission product behavior in gas cooled reactors IAEA-TECDOC-978, Nov. 1997

    Google Scholar 

  83. Private communications on melting of contaminated materials; private communications from. Company Siempelkamp, Germany

    Google Scholar 

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Kugeler, K., Zhang, Z. (2019). Operational Aspects. In: Modular High-temperature Gas-cooled Reactor Power Plant. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-662-57712-7_9

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  • DOI: https://doi.org/10.1007/978-3-662-57712-7_9

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