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

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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

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Calculation of Thermal Neutron Fluxes in Primary Shields

Calculation of Thermal Neutron Fluxes in Primary Shields PDF Author: D. C. Anderson
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 46

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A Simplified Theory of Neutron Attenuation and Its Application to Reactor Shield Design

A Simplified Theory of Neutron Attenuation and Its Application to Reactor Shield Design PDF Author: R. D. Albert
Publisher:
ISBN:
Category : Shielding (Radiation)
Languages : en
Pages : 40

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Book Description
A theory has been developed for the attenuation of neutrons in mixtures of hydrogenous and heavy materials primarily for use in connection with shielding designs. The theory is a simplified one which assumes a neutron is essentially lost after a single collision; an equivalent cross section which includes contributions to scattering by heavy materials is left adjustable in the theory. The procedure outlined in this paper involves comparison of the theory with experimental bulk shielding results to determine the adjustable parameter. Excellent agreement--for shielding purposes--has been obtained in this way with experimentally obtained spatial flux distributions for water, iron and water, and two lead and water shields of differing composition.

Calculation of Fast-neutron Flux Emerging from a Reactor Beamhole and Comparison with Experiment

Calculation of Fast-neutron Flux Emerging from a Reactor Beamhole and Comparison with Experiment PDF Author: Harvey S. Bloomfield
Publisher:
ISBN:
Category :
Languages : en
Pages : 28

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1166

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Radiation Shields and Shielding

Radiation Shields and Shielding PDF Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Shielding (Radiation)
Languages : en
Pages : 112

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Book Description
Included are 687 selected references to unclassified reports and scientific journal literature on radiation shields and shielding. Author, report number, and subject indexes are also included.

A Study of a Numerical Approach to Optimizing Reactor Shields with Respect to Weight and Volume

A Study of a Numerical Approach to Optimizing Reactor Shields with Respect to Weight and Volume PDF Author: Fred Channon
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 176

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Interim Studies of OMR for Marine Propulsion

Interim Studies of OMR for Marine Propulsion PDF Author: R. E. Stanbridge
Publisher:
ISBN:
Category : Marine nuclear reactor plants
Languages : en
Pages : 84

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Computational Methods in Reactor Shielding

Computational Methods in Reactor Shielding PDF Author: James Wood
Publisher: Elsevier
ISBN: 1483148130
Category : Technology & Engineering
Languages : en
Pages : 450

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Book Description
Computational Methods in Reactor Shielding deals with the mathematical processes involved in how to effectively control the dangerous effect of nuclear radiation. Reactor shielding is considered an important aspect in the operation of reactor systems to ensure the safety of personnel and others that can be directly or indirectly affected. Composed of seven chapters, the book discusses ionizing radiation and how it aids in the control and containment of radioactive substances that are considered harmful to all living things. The text also outlines the necessary radiation quantities and units that are needed for a systemic control of shielding and presents an examination of the main sources of nuclear radiation. A discussion of the gamma photon cross sections and an introduction to BMIX, a computer program used in illustrating a technique in identifying the gamma ray build-up factor for a reactor shield, are added. The selection also discusses various mathematical representations and areas of shielding theory that are being used in radiation shielding. The book is of great value to those involved in the development and implementation of systems to minimize and control the dangerous and lethal effect of radiation.

Analysis of Neutron Flux in the Shielding of the Sodium Reactor Experiment

Analysis of Neutron Flux in the Shielding of the Sodium Reactor Experiment PDF Author: F. L. Fillmore
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 34

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