Abstract
The main requirements on containments, which are the retention of radioactive substances and the protection against impacts from the outside, are explained. The different aspects between those buildings for LWR and for modular HTR are discussed. The LWR needs a dense containment, because large amounts of radioactive substance can be released into this room during many discussed accidents. In case of modular HTR, this release is very small. Technologies, which have been applied until now for the different HTR concepts, are described and evaluated. Especially HTR plants with large power and possibly large release rates of radioactivity from the primary circuit in case of very severe accidents need a dense containment. In case of modular HTR mainly the protection against impacts from the outside and the limitation of air ingress after depressurization accidents are important. This requirement is fulfilled by an inner dense concrete cell with self-acting closure after depressurization. This concept would allow an effective filtering for the outflowing gas from the inner cell. Different solutions for filtering which today already are realized in nuclear power plants are explained. Furthermore, some future possible improvements of designing plants against severe accidents are indicated. It will be possible to sample and store off-gases with radioactive contamination for sometime to utilize the storage time for the decay of some substances, like Iodine. Furthermore, underground siting can improve the protection against impacts from the outside. All improvements need optimization of the efforts with regard to economy and environmental aspects.
This is a preview of subscription content, log in via an institution to check access.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
References
Bohn T. (editor), Nuclear power plants, Vol. 10 of Handbook Series Energy, Technischer Verlag Resch, Verlag TÜB Rheinland, 1986
Lewis E.E., Nuclear power reactor safety, John Wiley + Sons, New York, Chicister, Brisbane, Toronto, 1977
Ziegler A., Reactor technology, Vol. 3 Technology of Power Stations, Springer Verlag, Berlin, Heidelberg, New York, Tokyo, 1985
Siemens AG/KWU, Nuclear power plants with pressurized water reactor plant, Description, Erlangen, May 1989
Eibel F.H., Schlüter H., Cüppers H., Hennies H.H., Keßler G., Containments for new PWR reactors, SMIRT 11 Post Conference Seminar on Probabilistic Safety Assessment Methodology, Tokyo, Aug. 1991
GRS, German risk study for nuclear power plants, Phase B, Verlag TÜV Rheinland, Köln, 1990
IAEA, Advanced nuclear plant design options to cape with external events, IAEA TECDOC-1489, Feb. 2006
Smidt D., Reactor safety technology, Springer Verlag, Berlin, Heidelberg, New York, 1979
RSK (Germany), Guidelines for accidents of pressurized water reactors, Ministry of Internal Affairs, Bonn, 1983
Hennies E.E., Kucera B., Status of the international research on reactor safety, KFK-Nachrichten, 1988
IAEA, Safety standards for protecting people and environment; storage of radioactive waste, IAEA, Vienna, 2006
Spiegelberg-Plauer R., Stern W., International reporting of nuclear and radiological events at the International Atomic Energy Agency, Atomwirtschaft, 52. Jg., Heft 2, 2007
Kuczera B., Innovative trends in the light water reactor technology, KFK-Nachrichten, Jg. 25, 4, 1993
INET, HTR-PM Project information 2008
Special issue, The AVR reactor, Atomwirtschaft, April 1968
Duffield R.B., Development of the high-temperature gas-cooled reactor and the Peach Bottom high-temperature gas-cooled reactor prototype, Journ. British Nucl. Energy Society, 5, 1966
Locket G.E., Huddle R.A.U., Development of the design of the high-temperature gas-cooled reactor experiment, Dragon Report 1, Jan. 1960
AVR experimental high-temperature reactor – 21 years of successful operation for a future energy technology, VDI-Verlag, Düsseldorf, 1990
Commission of European Community, Technical report of THTR prototype 300MWel, Vol. 1, 2, EUR2130, 1969
Olson H.G., et al, The Fort St. Vrain high-temperature gas-cooled reactor: Prestressed concrete reactor vessel (PCRV) performance, Nuclear Engineering and Design, 72, 1982
Special issue, Modern power stations, Vol. 7, Nuclear power generation, Pergamon Press, Oxford New York, Seoul, Tokyo, 1992
Burrow R.E.D., Williams A.J., Hartlepool AGR – reactor pressure vessel, Nuclear Engineering International 14, 1969
Special issue, BBC/HRB, The HTR 100MWel: concept, technology, time plans, costs, Mannheim, July 1981
Special issue, The future of the HTR technology, VGB Kraftwerkstechnik 65, Vol., Jan. 1985; Vol. 3: March 1985
R. Schulten etal. Industrial power plant with high temperature reactor PR500-OTTO-principle-for production of process steam, JÜL-941-RG, April 1973
Siemens/Interatom, The high-temperature modular nuclear power plant, Vol. 1,2, Jan. 1984
Special issue, The Chinese high-temperature reactor HTR-10 the first inherently safe generation IV nuclear power plant, Nuclear Engineering and Design, Vol.???, 218, No. 1–3, Oct. 2002
Shiozawa S., The HTR program in Japan and the HTTR project, ECN-R-95-026, Petten, Sept. 1995
Dillmann H.G., Pasler H., Wilhelm J.G., Containment venting filter designs incorporation – stainless steel fiber filters, Kerntechnik 53, No. 1, 1988
Eckhardt B., Containment venting for light water reactor plants, Kerntechnik 53, 1988, 81
Speyer K., Gremm R., Krugmann U., Roth-Seefrid H., Accident management measures for KWU nuclear power plants, Kerntechnik 50, 1987
Gräsund C., Johansson K., Nilsson L., Tiren I., FILTRA, Filtered atmospheric venting of LWR containments: a status report, CN-39/74, 1980
Dorman R.G., A comparison of the methods used in the nuclear industry to test high-efficiency filters, Commissions of the European Communities, V/3603/81 EN, June 1981
Eckhardt B., Process technology and verification program for PWR and BWR containment venting, CSNI Specialist Meeting, Paris, May 17–18, 1988
Czech J., Roth-Seefrid H., Promises, planning principles and examples of accident management, Kerntechnik 53, No. 1, 1998
Czech J., Fabian H., Gast P., Gremm O., Mitigation of severe accident consequences by the containment design of German LWR, 2nd Int. Seminar on Containment of Nuclear Reactors, held in conjunction with the 9th Int. Conf. on Structural Mechanics in Reactor Technology, Lausanne, Switzerland, Aug. 24–25, 1987
Wilhelm J.G., Iodine filters in nuclear installations commission of the European communities, Luxemburg, Oct. 1982
El-Kawankey S., comparison of modern concepts for the separation of the fine dust, Study, RWTH Aachen, April 2008
Hake G., The relation of reactor design to siting and containment in Canada, in Proceedings: Containment and Siting of Nuclear Power Plants, IAEA, Vienna, 1967
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
Copyright information
© 2019 Tsinghua University Press, Beijing and Springer-Verlag GmbH Germany
About this chapter
Cite this chapter
Kugeler, K., Zhang, Z. (2019). Reactor Containment Building. In: Modular High-temperature Gas-cooled Reactor Power Plant. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-662-57712-7_7
Download citation
DOI: https://doi.org/10.1007/978-3-662-57712-7_7
Published:
Publisher Name: Springer, Berlin, Heidelberg
Print ISBN: 978-3-662-57710-3
Online ISBN: 978-3-662-57712-7
eBook Packages: EnergyEnergy (R0)