Abstract
The most important reactor physics characteristics needed for the understanding of the design and operation of nuclear reactors and of their fuel cycle are presented. This comprises the criticality factor, the neutron and temperature distributions in the reactor core and reactivity effects to be controlled by the safety systems. The evolution of the isotopic composition during burnup, i.e., the buildup of fission products and actinides in the reactor fuel, and the importance of conversion and breeding ratios are discussed together with the fuel utilization. Inherent safety characteristics like the negative fuel Doppler coefficient and the negative coolant temperature coefficient are essential for the safe operation and control of nuclear reactors.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Notes
- 1.
1 eV = 1.602 \(\times \) 10\(^{-19}\) J is the kinetic energy acquired by an electron passing through a potential gradient of 1 V. 1 keV is equal to 10\(^{3}\) eV and 1 MeV is equal to 10\(^{6}\) eV. The energy of 0.0253 eV corresponds to a neutron velocity of 2,200 m/s.
References
Weinberg AM, Wigner EP (1958) The physical theory of neutron chain reactors. University of Chicago Press, Chicago
Glasstone S, Edlund MC (1952) Nuclear reactor theory. D. Van Nostrand, Princeton
Lamarsh JR (1983) Introduction to nuclear reactor theory, 2nd edn. Addison-Wesley, Reading
Duderstadt JJ, Hamilton LJ (1976) Nuclear reactor analysis. Wiley, New York
Henry AF (1975) Nuclear-reactor analysis. MIT Press, Cambridge
Bell GI, Glasstone S (1970) Nuclear reactor theory. Van Nostrand Reinhold, New York
Meghreblian RV, Holmes DK (1960) Reactor analysis. McGraw-Hill, New York, pp 160–267 and 626–747
Radkowsky A (ed) (1964) Naval reactors physics handbook. U.S. Atomic Energy Commission, Washington, DC (Chap. 5)
Ott K et al (1983) Introductory nuclear reactor statics. American Nuclear Society, LaGrange Park
Michaudon A (1981) Nuclear fission and neutron induced fission cross sections. Pergamon Press, Oxford
Broeders CHM (2010) Personal communication, KIT Karlsruhe
Keepin GR (1965) Physics of nuclear kinetics. Addison-Wesley, Reading
Ash M (1965) Nuclear reactor kinetics. McGraw-Hill, New York
Hetrick DL (ed) (1972) Dynamics of nuclear systems. University of Arizona Press, Tucson
ANS-5.1-1994 (1985) Element standard, revision of ANSE/ANS-51-1979; R 1985
Nusbaumer O (2006) Decay heat in nuclear reactors. http://decay-heat.tripod.com/
Rineiski A (2008) Decay heat production and TRU burner. Prog Nucl Energy 50:377–381
Koning A et al (2006) The JEFF-3.1 nuclear data library, JEFF report 21, NEA No. 6190, OECD/NEA, Paris
Roussin RW, Young PG, McKnight R (1994) Current status of ENDF/B-VI. In: Proceedings of the international conference on nuclear data for science and technology, vol 2. Gatlinburg, p 692
Kikuchi Y (1994) JENDL-3, Revision 2: JENDL 3-2. In: Proceedings of the international conference on nuclear data for science and technology, vol. 2. Gatlinburg, p 685
Askew J et al (1966) A general description of the lattice code WIMS. J Br Nucl Energy Soc 5:564
Bondarenko I et al (1964) Group constants for nuclear reactor calculations. Translation–consultants Bureau Enterprice Inc., New York
Lewis EE, Miller WF (1993) Computational methods of neutron transport. Wiley-Interscience, New York (1984); reprinted by American Nuclear Society, LaGrange Park
Ronen Y (ed) (1986) CRC handbook of nuclear reactors calculations, vol I. CRC Press, Boca Raton
Alcouffe RE et al (1995) DANTSYS: a diffusion accelerated neutral particle transport code system, LA-12969-M. Los Alamos National Laboratory, Los Alamos
Lawrence RD (1983) The DIF3D nodal neutronics option for two- and three-dimensional diffusion theory calculations in hexagonal geometry, ANL-83-1. Argonne National Laboratory, Argonne
Briesmeister JF (ed) (2000) MCNP–a general Monte Carlo N-particle transport code, version 4C. Technical report, LA-13709-M. Los Alamos National Laboratory, USA
Oldekop W (1975) Einführung in die Kernreaktor- und Kernkraftwerkstechnik, Teil I. Karl Thiemig, München
Kessler G (1983) Nuclear fission reactors. Springer, Vienna
Waltar A et al (1981) Fast breeder reactors. Pergamon Press, New York
Stacey W (2007) Nuclear reactor physics. Wiley, New York
Wiese HW, Fischer U (1981) KORIGEN—Ein Programm zur Bestimmung des nuklearen Inventars von Reaktorbrennstoffen im Brennstoffkreislauf. Kernforschungszentrum Karlsruhe, KfK-3014
Haeck W et al (2007) An optimum approach to Monte Carlo burnup. Nucl Sci Eng 156:180–196
Fission Product Nuclear Data (FPND)—1977 (1978) In: Proceedings of the second advisory group meeting on fission product nuclear data, Energy Centrum Netherlands, Petten, 5–9 September 1977. International Atomic Energy Agency, IAEA-213, Vienna
ORNL (2005) SCALE a modular code system for performing standardized computer analyses for licensing evaluations, ORNL/TM-2005/39, version 5, vols I–III
Poston DI et al (1999) Development of a fully-automated Monte Carlo burnup code MONTEBURNS, LA-UR-99-42
Heusener G (1980) Personal communication, KfK Karlsruhe
Hummel H et al (1970) Reactivity coefficients in large fast power reactors. American Nuclear Society, LaGrange Park
Nicholson R et al (1968) The doppler effect in fast reactors, advances in nuclear science and technology, vol 4. Academic Press, New York, p 109
Ott K et al (1985) Nuclear reactor dynamics. American Nuclear Society, LaGrange Park
Author information
Authors and Affiliations
Rights and permissions
Copyright information
© 2012 Springer-Verlag Berlin Heidelberg
About this chapter
Cite this chapter
Kessler, G. (2012). Some Basic Physics of Converters and Breeder Reactors. In: Sustainable and Safe Nuclear Fission Energy. Power Systems. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-11990-3_3
Download citation
DOI: https://doi.org/10.1007/978-3-642-11990-3_3
Published:
Publisher Name: Springer, Berlin, Heidelberg
Print ISBN: 978-3-642-11989-7
Online ISBN: 978-3-642-11990-3
eBook Packages: EngineeringEngineering (R0)