Diffusion of Thermal Neutrons

Diffusion of Thermal Neutrons PDF Author: A. M. Weinberg
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 8

Get Book Here

Book Description

Diffusion of Thermal Neutrons

Diffusion of Thermal Neutrons PDF Author: A. M. Weinberg
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 8

Get Book Here

Book Description


Thermal Neutron Diffusion Length Measurements in Light Water from 20 C to 90 C.

Thermal Neutron Diffusion Length Measurements in Light Water from 20 C to 90 C. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Get Book Here

Book Description
The diffusion length of thermal neutrons in light water was measured as a function of temperature in the range 20 to 90 un. Concent 85% C for both pure water and poison solutions. Various concertrations of three poisons and up to st r H/sub 3/BO/sub 3/, CdSO/sub 4/, and Gd(NO/sub 3/)/sub 3/--were used in this experiment. The thermal neutron source was the thermal column of the General Electric Nuclear Test Reactor. The Water Gun'' apparatus was utilized for the measurements. (auth).

A Determination of the Diffusion Length of Thermal Neutrons in the X-10 Standard Graphite Pile

A Determination of the Diffusion Length of Thermal Neutrons in the X-10 Standard Graphite Pile PDF Author: E. D. Klema
Publisher:
ISBN:
Category : Thermal neutrons
Languages : en
Pages : 22

Get Book Here

Book Description


Thermal Neutron Diffusion Length Measurements in Light Water from 20°C to 90°C

Thermal Neutron Diffusion Length Measurements in Light Water from 20°C to 90°C PDF Author: John L. Russell
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 28

Get Book Here

Book Description


Neutron Diffusion

Neutron Diffusion PDF Author: S. Chakraverty
Publisher: CRC Press
ISBN: 1351667505
Category : Mathematics
Languages : en
Pages : 216

Get Book Here

Book Description
This book is designed for a systematic understanding of nuclear diffusion theory along with fuzzy/interval/stochastic uncertainty. This will serve to be a benchmark book for graduate & postgraduate students, teachers, engineers and researchers throughout the globe. In view of the recent developments in nuclear engineering, it is important to study the basic concepts of this field along with the diffusion processes for nuclear reactor design. Also, it is known that uncertainty is a must in every field of engineering and science and, in particular, with regards to nuclear-related problems. As such, one may need to understand the nuclear diffusion principles/theories corresponding with reliable and efficient techniques for the solution of such uncertain problems. Accordingly this book aims to provide a new direction for readers with basic concepts of reactor physics as well as neutron diffusion theory. On the other hand, it also includes uncertainty (in terms of fuzzy, interval, stochastic) and their applications in nuclear diffusion problems in a systematic manner, along with recent developments. The underlying concepts of the presented methods in this book may very well be used/extended to various other engineering disciplines viz. electronics, marine, chemical, mining engineering and other sciences such as physics, chemistry, biotechnology etc. This book then can be widely applied wherever one wants to model their physical problems in terms of non-probabilistic methods viz. fuzzy/stochastic for the true essence of the real problems.

Theory of Neutron Chain Reactions

Theory of Neutron Chain Reactions PDF Author: Alvin Martin Weinberg
Publisher:
ISBN:
Category : Diffusion
Languages : en
Pages : 204

Get Book Here

Book Description


Experimental and Theoretical Investigation of the Diffusion Length of Thermal Neutrons in Graphite

Experimental and Theoretical Investigation of the Diffusion Length of Thermal Neutrons in Graphite PDF Author: Richard Edward Kaiser
Publisher:
ISBN:
Category : Graphite
Languages : en
Pages : 195

Get Book Here

Book Description


Proceedings of the Brookhaven Conference on Neutron Thermalization: Theoretical aspects of transient and asymptotic phenomena

Proceedings of the Brookhaven Conference on Neutron Thermalization: Theoretical aspects of transient and asymptotic phenomena PDF Author: Brookhaven National Laboratory
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 350

Get Book Here

Book Description


Neutron Physics

Neutron Physics PDF Author: Karl-Heinrich Beckurts
Publisher: Springer Science & Business Media
ISBN: 3642876145
Category : Science
Languages : en
Pages : 455

Get Book Here

Book Description
This book is based upon a series of lectures I have occasionally given at the University of Gottingen since 1951. They were meant to introduce the students of experimental physics to the work in a neutron physics laboratory dealing with the problem of measuring neutron flux, diffusion length, Fermi age, effective neutron temperature, absorption cross sections and similar problems. Moreover, these lectures were intended to prepare the students for a subsequent lecture covering the physics of nuclear reactors. The original character of this series of lectures has been retained in the book. It is intended for use by students as well as anyone desiring to work on neutron physics measurements. The first half mainly covers the theory of neutron fields, i. e. essentially diffusion and slowing down theory. The second half is largely concerned with measurements in neutron fields. The appendix contains information and data which, in our experience, are frequently required in a neutron laboratory. The field of nuclear physics proper is briefly touched upon in the first two chapters, but only to the extent necessary for the understanding of the following chapters. The multitude of applications of neutron radiation has not been covered. The conclusion of this manuscript coincided with the end of my long period of activity with the Max-Planck-Institut fur Physik at Gottingen. To Professor HEISENBERG lowe thanks for his advice and suggestions for many of the subjects treated here.

Application of Fast Neutron Removal Theory to the Calculation of Thermal Neutron Flux Distributions in Reactor Shields

Application of Fast Neutron Removal Theory to the Calculation of Thermal Neutron Flux Distributions in Reactor Shields PDF Author: D. S. Duncan
Publisher:
ISBN:
Category : Nuclear merchant ships
Languages : en
Pages : 46

Get Book Here

Book Description