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Erschienen in:

2017 | OriginalPaper | Buchkapitel

1. Neutron Physics Background

verfasst von : Bahman Zohuri

Erschienen in: Neutronic Analysis For Nuclear Reactor Systems

Verlag: Springer International Publishing

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Abstract

This chapter introduces fundamental properties of the neutron. It covers reactions induced by neutrons, nuclear fission, slowing down of neutrons in infinite media, diffusion theory, the few-group approximation, point kinetics, and fission product poisoning. It emphasizes the nuclear physics bases of reactor design and its relationship to reactor engineering problems.

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Nächstes Kapitel Modeling Neutron Transport and Interactions

Nur mit Berechtigung zugänglich

You can get the data from http://ie.lbl.gov/toimass.html

The speed of neutrons in a reactor is sufficiently low that one can neglect relativistic effects therefore m = m ₀, the neutron rest mass (1.6748 × 10⁻²⁷ kg).

FEMP computer code has been developed by Professor Patrick McDaniel of University of New Mexico, Nuclear Engineering Department.

This effort was taken in place under contract by McDaniel and Zohuri in time period of 2001–2003 but never was a finished effort, although a lot of work was put into it and somewhat a new modified version NJOY with recoil capability was developed.

One can calculate the total binding energy of a nucleus from the mass defect, Δm which is the difference between the mass of the bound nucleus and the sum of the masses of the nucleons, using Einstein’s equation \( {E}_{{\mathrm{b}}_{\mathrm{Total}}}=\Delta m{c}^2 \).

P.E. Hodgson, E. Gadioli, E. Gadioli Erb, Introductory Nuclear Physics (Oxford Science Publications, Oxford, 1997)

D.G. Madland, J. Rayford Nix, New calculation of prompt fission neutron spectra and average prompt neutron multiplicities. Nucl. Sci. Eng. 81, 213–271 (1982)CrossRef

J. Lewins, Nuclear Reactor Kinetics and Control (Pergamon Press, Oxford, 1978)

K. Ott, R.J. Neuhold, Nuclear Reactor Dynamics (American Nuclear Society, LaGrange Park, 1985)

R.J. LaBauve, T.R. England, D.C. George, C.W. Maynard, Fission product analytic impulse source functions. Nucl. Technol. 56, 332–339 (1982)

A.F. Henry, Nuclear Reactor Analysis (The MIT Press, Cambridge, 1975)

J.R. Lamarsh, Introduction to Nuclear Reactor Theory (Addison Wesley, Boston, 1966)

B. Zohuri, Combined Cycle Driven Efficiency for Next Generation Nuclear Power Plants: An Innovative Design Approach (Springer, New York, 2015)CrossRef

B. Zohuri, P. McDaniel, A comparison of a recuperated open cycle (air) brayton power conversion system with the traditional steam rankine cycle for the next generation nuclear power plant. Nucl. Sci., October 2015

10.

B. Zohuri, Innovative Open Air Brayton Combined Cycle Systems for the Next Generation Nuclear Power Plants (University of New Mexico Publications, Albuquerque, 2014)

11.

P.J. McDaniel, B. Zohuri, C.R.E. de Oliveira, in A Combined Cycle Power Conversion System for Small Modular LMFBRs, ANS Transactions, September 2014

12.

Cycle Power Conversion System for the Next Generation Nuclear Power Plan, ANS Transactions, November 2012

13.

C. Forsberg, P. McDaniel, B. Zohuri, Variable electricity and steam from salt, helium, and sodium cooled base-load reactors with gas turbines and heat storage, in Proceedings of ICAPP 2015

Titel: Neutron Physics Background
verfasst von: Bahman Zohuri
Verlag: Springer International Publishing
Buch: Neutronic Analysis For Nuclear Reactor Systems
Print ISBN: 978-3-319-42962-5

Electronic ISBN: 978-3-319-42964-9

Copyright-Jahr: 2017
DOI: https://doi.org/10.1007/978-3-319-42964-9_1