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2018 | OriginalPaper | Chapter

Fission Reactor Physics

Author : Michael Natelson

Published in: Nuclear Energy

Publisher: Springer New York

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Excerpt

Fissile
Fissile isotopes are fissionable by the capture of neutrons of any energy, but are especially easily fissioned by the capture of slow neutrons, for example, U233, U235, Pu239, and Pu241.
Fertile
Fertile isotopes may be transmuted into fissile isotopes by neutron capture. The naturally occurring fertile isotopes are Th232 and U238.
Critical
A critical fission reactor is in a steady state, with its neutron population sustained by a chain reaction.
Reactivity
Reactivity is a dimensionless parameter, which characterizes how far from critical a fission reactor is. If zero, the reactor is critical; if positive, the reactor is supercritical and its neutron population is increasing; if negative, the reactor is subcritical.
Microscopic cross section
A microscopic cross section is a parameter, with dimensions of area, that is a measure of the probability of a particular reaction resulting from an incident particle on a target nucleus. The macroscopic cross section for this “particular” reaction is the microscopic cross section times the number density of the target nucleus.

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Literature
1.
go back to reference Wheeler JA (1967) Mechanism of fission. Phys Today 20(11):49–52 Wheeler JA (1967) Mechanism of fission. Phys Today 20(11):49–52
2.
go back to reference Bohr N, Wheeler JA (1939) The mechanism of nuclear fission. Phys Rev 56:426CrossRef Bohr N, Wheeler JA (1939) The mechanism of nuclear fission. Phys Rev 56:426CrossRef
3.
go back to reference Ford KW (2009) Wheeler’s work on particles, nuclei, and weapons. Phys Today 62(4):29CrossRef Ford KW (2009) Wheeler’s work on particles, nuclei, and weapons. Phys Today 62(4):29CrossRef
4.
go back to reference Fermi E, Szilard L (1955) Neutronic reactor. US Patent 2,708,656, 17 May 1955 Fermi E, Szilard L (1955) Neutronic reactor. US Patent 2,708,656, 17 May 1955
5.
go back to reference Einstein A (1905) On the electrodynamics of moving bodies. Ann Phys 17:891–921CrossRef Einstein A (1905) On the electrodynamics of moving bodies. Ann Phys 17:891–921CrossRef
6.
go back to reference Frankel S, Metropolis N (1947) Calculations in the liquid-drop model of fission. Phys Rev 72:914CrossRef Frankel S, Metropolis N (1947) Calculations in the liquid-drop model of fission. Phys Rev 72:914CrossRef
7.
go back to reference Kinsey R (1979) Compiler “ENDF/B Summary Doc.” BNL-NCS-17541(ENDF-201), 3rd edn. ENDF/B-V, Brookhaven National Laboratory, Upton Kinsey R (1979) Compiler “ENDF/B Summary Doc.” BNL-NCS-17541(ENDF-201), 3rd edn. ENDF/B-V, Brookhaven National Laboratory, Upton
8.
go back to reference England TR, Wilson WB, Stamatelatos MG (1976) Fission product data for thermal reactors. EPRI-NP-356, Los Alamos Scientific Lab., New Mexico England TR, Wilson WB, Stamatelatos MG (1976) Fission product data for thermal reactors. EPRI-NP-356, Los Alamos Scientific Lab., New Mexico
9.
go back to reference Parks DE, Nelkin MS, Wikner NF, Beyster JR (1970) Slow neutron scattering and thermalization with reactor applications. Benjamin, New York Parks DE, Nelkin MS, Wikner NF, Beyster JR (1970) Slow neutron scattering and thermalization with reactor applications. Benjamin, New York
10.
go back to reference MacFarlane RE (1994) The NJOY nuclear data processing system, Version 91, report #LA-12740-M. Los Alamos National Laboratory, New Mexico MacFarlane RE (1994) The NJOY nuclear data processing system, Version 91, report #LA-12740-M. Los Alamos National Laboratory, New Mexico
11.
13.
go back to reference Larson NM (2006) Updated user’s guide for SAMMY: multilevel R-matrix fits to neutron data using Bayes’s equations, ORNL/TM-9179/R7. Oak Ridge National Lab, OakRidge Larson NM (2006) Updated user’s guide for SAMMY: multilevel R-matrix fits to neutron data using Bayes’s equations, ORNL/TM-9179/R7. Oak Ridge National Lab, OakRidge
14.
go back to reference Spanier J, Gelbard EM (1969, 2008) Monte carlo principles and neutron transport problems. Dover/Addison-Wesley, New York/Reading Spanier J, Gelbard EM (1969, 2008) Monte carlo principles and neutron transport problems. Dover/Addison-Wesley, New York/Reading
15.
go back to reference X-5 Monte Carlo Team (2003) MCNP – A general Monte Carlo N-Particle transport code, Version 5, LA-UR-03-1987. Los Alamos National Laboratory, New Mexico X-5 Monte Carlo Team (2003) MCNP – A general Monte Carlo N-Particle transport code, Version 5, LA-UR-03-1987. Los Alamos National Laboratory, New Mexico
16.
go back to reference Ondis LA II, Tyburski LJ, Moskowitz BS (2000) RCP01 – a Monte Carlo program for solving neutron and photon transport problems in three dimensional geometry with detailed energy description and depletion capability, B-TM-1638. Bettis Atomic Power Laboratory, West Mifflin Ondis LA II, Tyburski LJ, Moskowitz BS (2000) RCP01 – a Monte Carlo program for solving neutron and photon transport problems in three dimensional geometry with detailed energy description and depletion capability, B-TM-1638. Bettis Atomic Power Laboratory, West Mifflin
18.
go back to reference Lathrop KA (1972) Discrete-ordinates methods for the numerical solution of the transport equation. Reactor Technol 15:107 Lathrop KA (1972) Discrete-ordinates methods for the numerical solution of the transport equation. Reactor Technol 15:107
19.
20.
go back to reference Varga RS (2000) Matrix iterative analysis, 2 revised and expandedth edn. Springer, HeidelbergCrossRef Varga RS (2000) Matrix iterative analysis, 2 revised and expandedth edn. Springer, HeidelbergCrossRef
21.
go back to reference Henry A, Dias A, Frances W, Parlos A, Tanker E, Tanker Z (1986) Continued development of nodal methods for nuclear reactor analysis, MIT EL 86–002. Massachusetts Institute of Technology, Cambridge Henry A, Dias A, Frances W, Parlos A, Tanker E, Tanker Z (1986) Continued development of nodal methods for nuclear reactor analysis, MIT EL 86–002. Massachusetts Institute of Technology, Cambridge
22.
go back to reference Buslik AJ, Weinreich WA (1967) Variational calculation of complex natural modes of xenon oscillation, WAPD -TM-673 (LWB-LSBR Development Program). Bettis Atomic Power Laboratory, West Mifflin Buslik AJ, Weinreich WA (1967) Variational calculation of complex natural modes of xenon oscillation, WAPD -TM-673 (LWB-LSBR Development Program). Bettis Atomic Power Laboratory, West Mifflin
24.
go back to reference Thie JA (1963) Reactor noise (an AEC monograph). Rowman and Littlefield, New York Thie JA (1963) Reactor noise (an AEC monograph). Rowman and Littlefield, New York
25.
go back to reference Osborn RK, Yip S (1966) Foundations of neutron transport theory, Monograph series on nuclear technology. Gordon and Breach, New York Osborn RK, Yip S (1966) Foundations of neutron transport theory, Monograph series on nuclear technology. Gordon and Breach, New York
26.
go back to reference Natelson M, Osborn RK, Shure S (1966) Space and energy effects in reactor fluctuation experiments. J Nucl Energy Parts A/B 20(7):557–585CrossRef Natelson M, Osborn RK, Shure S (1966) Space and energy effects in reactor fluctuation experiments. J Nucl Energy Parts A/B 20(7):557–585CrossRef
27.
go back to reference Hurwitz H Jr, MacMillan DB, Smith JH, Storm ML (1963) Kinetics of low source reactor startups, part I and II. Nucl Sci Eng 15:166CrossRef Hurwitz H Jr, MacMillan DB, Smith JH, Storm ML (1963) Kinetics of low source reactor startups, part I and II. Nucl Sci Eng 15:166CrossRef
28.
go back to reference Clark WG, Harris DR, Natelson M, Walter JF (1968) Variances and covariances of neutron and precursor populations in time-varying reactors. Nucl Sci Eng 31:440–457CrossRef Clark WG, Harris DR, Natelson M, Walter JF (1968) Variances and covariances of neutron and precursor populations in time-varying reactors. Nucl Sci Eng 31:440–457CrossRef
29.
go back to reference Sutton TM et al, Knolls Atomic Power Lab., Griesheimer DP et al, Bettis Atomic Power Lab (2007) The MC21 Monte Carlo Code, LM-06K144, Proceedings (on CD-ROM) of the joint international topical meeting on M&C and supercomputing applications, Monterey Sutton TM et al, Knolls Atomic Power Lab., Griesheimer DP et al, Bettis Atomic Power Lab (2007) The MC21 Monte Carlo Code, LM-06K144, Proceedings (on CD-ROM) of the joint international topical meeting on M&C and supercomputing applications, Monterey
30.
go back to reference Palmiotti G et al, Argonne National Lab (2007) UNIC Ultimate Neutronic Investigation Code, Proceeding (on CD-ROM) of the joint international topical meeting on M&C and supercomputing applications, Monterey Palmiotti G et al, Argonne National Lab (2007) UNIC Ultimate Neutronic Investigation Code, Proceeding (on CD-ROM) of the joint international topical meeting on M&C and supercomputing applications, Monterey
31.
go back to reference Herman M et al (2008) Covariance evaluation methodology for neutron cross sections, BNL-81525-2008. Brookhaven National Lab, Upton Herman M et al (2008) Covariance evaluation methodology for neutron cross sections, BNL-81525-2008. Brookhaven National Lab, Upton
32.
go back to reference Belle J, Berman RM (eds) (1984) Chapter 2, Natelson M, Nuclear properties of the thorium fuel cycle. In: Thorium dioxide: properties and nuclear applications. Naval Reactors Office, U. S. Department of Energy, Govt. Printing Office, Washington, DC Belle J, Berman RM (eds) (1984) Chapter 2, Natelson M, Nuclear properties of the thorium fuel cycle. In: Thorium dioxide: properties and nuclear applications. Naval Reactors Office, U. S. Department of Energy, Govt. Printing Office, Washington, DC
33.
go back to reference Katcoff S (1958) Fission-Product yields from U, Th and Pu. Nucleonics 16(4):78 Katcoff S (1958) Fission-Product yields from U, Th and Pu. Nucleonics 16(4):78
go back to reference Duderstadt JJ, Hamilton LJ (1976) Nuclear reactor analysis. Wiley, New York Duderstadt JJ, Hamilton LJ (1976) Nuclear reactor analysis. Wiley, New York
go back to reference Henry AF (1975) Nuclear-reactor analysis. MIT Press, Cambridge Henry AF (1975) Nuclear-reactor analysis. MIT Press, Cambridge
go back to reference Kaplan I (1962) Nuclear physics, 2nd edn. Addison-Wesley, ReadingMATH Kaplan I (1962) Nuclear physics, 2nd edn. Addison-Wesley, ReadingMATH
go back to reference Krane KS (1988) Introductory nuclear physics. Wiley, New York Krane KS (1988) Introductory nuclear physics. Wiley, New York
go back to reference Mermin ND (2005) It’s about time, understanding Einstein’s relativity. Princeton University Press, PrincetonMATH Mermin ND (2005) It’s about time, understanding Einstein’s relativity. Princeton University Press, PrincetonMATH
Metadata
Title
Fission Reactor Physics
Author
Michael Natelson
Copyright Year
2018
Publisher
Springer New York
DOI
https://doi.org/10.1007/978-1-4939-6618-9_18