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NEUTRON PHYSICS FOR NUCLEAR REACTORS
Unpublished Writings by Enrico Fermi
by S Esposito (Università di Napoli "Federico II", Italy
& INFN Sezione di Napoli, Italy) & O Pisanti (Università
di Napoli "Federico II", Italy & INFN Sezione di Napoli, Italy)
704pp
978-981-4291-22-4: US$111 / £76 US$83.25
/ £57
978-981-4291-23-1(ebook): US$144 US$108
Table
of Contents (253k)
Introduction
(302k)
Chapter
1: Sources of Neutrons (172k)
This unique volume gives an accurate and very detailed
description of the functioning and operation of basic nuclear reactors,
as emerging from yet unpublished papers by Nobel Laureate Enrico Fermi.
In the first part, the entire course of lectures on Neutron
Physics delivered by Fermi at Los Alamos is reported, according to the
version made by Anthony P French. Here, the fundamental physical
phenomena are described very clearly and comprehensively, giving the
appropriate physics grounds for the functioning of nuclear piles. In
the second part, all the patents issued by Fermi (and coworkers) on the
functioning, construction and operation of several different kinds of
nuclear reactors are reported. Here, the main engineering problems are
encountered and solved by employing simple and practical methods, which
are described in detail.
This seminal work mainly caters to students, teachers and
researchers working in nuclear physics and engineering, but it is of
invaluable interest to historians of physics too, since the material
presented here is entirely novel.
Contents:
- Introduction
- Neutron Physics:
- The Isotopic Chart: Nuclear Masses and
Energies
- The Scattering of Neutrons (Part 1)
- Resonance: Models of the Nucleus
- The Scattering of Neutrons (Part 2)
- The Slowing Down of Neutrons
- Thermal Neutron Distributions
- The Reflection of Neutrons
- The Possibility of a Chain Reaction
- The Time Dependence of a Pile
- Practical Aspects of Pile Physics
- Nuclear Reactors:
- Process for the Production of Radioactive
Substances
- Method of Operating a Neutronic Reactor
- Air Cooled Neutronic Reactor
- Testing Material in a Neutronic Reactor
- Neutron Velocity Selector
- Method of Testing Thermal Neutron
Fissionable Material for Purity
- Method of Sustaining a Neutronic Chain
Reacting System
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