Calculations of Thermal-neutron Flux Distributions in Concrete-walled Ducts Using an Albedo Model with Monte Carlo Techniques PDF Download

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Calculations of Thermal-neutron Flux Distributions in Concrete-walled Ducts Using an Albedo Model with Monte Carlo Techniques

Calculations of Thermal-neutron Flux Distributions in Concrete-walled Ducts Using an Albedo Model with Monte Carlo Techniques PDF Author: V. R. Cain
Publisher:
ISBN:
Category : Air ducts
Languages : en
Pages : 200

Book Description


Calculations of Thermal-neutron Flux Distributions in Concrete-walled Ducts Using an Albedo Model with Monte Carlo Techniques

Calculations of Thermal-neutron Flux Distributions in Concrete-walled Ducts Using an Albedo Model with Monte Carlo Techniques PDF Author: V. R. Cain
Publisher:
ISBN:
Category : Air ducts
Languages : en
Pages : 200

Book Description


Calculations of Thermal-Neutron Flux Distributions in Concrete-Walled Ducts Using an Albedo Model with Monte Carlo Techniques

Calculations of Thermal-Neutron Flux Distributions in Concrete-Walled Ducts Using an Albedo Model with Monte Carlo Techniques PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
BS>When radiation shields are penetrated by ducts, the gamma rays resulting from the radiative capture of lowenergy neutrons in the duct walls can be principal contributors to the total dose along the duct. In order to calculate the effect of these capture gamma rays, the distribution of low-energy neutrons in the ducts must be known. This report presents calculations of low- energy neutron distributions in concrete-walled ducts by a method in which an albedo model and a Monte Carlo technique were used. One series of calculations was performed for straight ducts so that comparisons could be made with the Simon- Clifford analytic approximation. Another series was for threelegged rectangular ducts similar to those used in a Tower Shielding Facility experiment. When au albedo similar to that to be expected for a pure thermal-neutron source was used, the results agreed very closely wilh the TSF data. A digital computer code was written to perform the calculations. (auth).

Calculations Using the Albedo Concept of the Subcadmium Flux Along the Center Line of

Calculations Using the Albedo Concept of the Subcadmium Flux Along the Center Line of PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 31

Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1176

Book Description
NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.

Monte Carlo Calculations, Using the Albedo Concept, of the Fast-neutron Dose Rates Along the Center Lines of One- and Two-legged Square Concrete Open Ducts and Comparison with Experiment

Monte Carlo Calculations, Using the Albedo Concept, of the Fast-neutron Dose Rates Along the Center Lines of One- and Two-legged Square Concrete Open Ducts and Comparison with Experiment PDF Author: R. E. Maerker
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 20

Book Description


Calculations, Using the Albedo Concept, of Thermal-neutron Fluxes, Epicadmium-neutron Fluxes, and Fast-neutron Dose Rates Along the Center Lines of Square Concrete Ducts

Calculations, Using the Albedo Concept, of Thermal-neutron Fluxes, Epicadmium-neutron Fluxes, and Fast-neutron Dose Rates Along the Center Lines of Square Concrete Ducts PDF Author: R. E. Maerker
Publisher:
ISBN:
Category :
Languages : en
Pages : 79

Book Description
Monte Carlo calculations that use the albedo concept and a particularly demanding source geometry and spectrum were carried out to determine subcadmium- and epicadmium-neutron fluxes and fast-neutron dose rates along the center lines of one-, two-, and three-legged square concrete ducts open on the source end. Secondary gamma-ray dose rates arising from the capture of neutrons in the duct walls were also calculated. The calculations used previously reported albedo data that are differential in both the reflected angles and the reflected energy. A comparison of the calculated neutron fluxes and dose rates with those obtained in geometrically identical experiments conducted at the Tower Shielding Facility shows agreement generally within 25 percent through five orders of duct attenuation. The results thus place on a firm foundation the method of treating neutron transmission through large-sized ducts as a multiple-reflection phenomenon describable by the differential albedo properties of the walls. The conclusion is also reached that wall-capture gamma-ray dose rates arising from capture of thermal-neutrons and the dose from the thermal neutrons themselves (whether due to an epicadmium source or a subcadmium source) can comprise a very important part of the total absorbed dose rate in tissue at locations deep inside a multilegged duct. (Author).

Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1330

Book Description


Advances in Nuclear Science and Technology

Advances in Nuclear Science and Technology PDF Author: Ernest J. Henley
Publisher: Elsevier
ISBN: 1483215628
Category : Technology & Engineering
Languages : en
Pages : 396

Book Description
Advances in Nuclear Science and Technology, Volume 5 presents the underlying principles and theory, as well as the practical applications of the advances in the nuclear field. This book reviews the specialized applications to such fields as space propulsion. Organized into six chapters, this volume begins with an overview of the design and objective of the Fast Flux Test Facility to provide fast flux irradiation testing facilities. This text then examines the problem in the design of nuclear reactors, which is the analysis of the spatial and temporal behavior of the neutron and temperature distributions within the system. Other chapters consider the three major ways of estimating shield effectiveness. This book discusses as well the purpose of variational principle, which is a characterization of a function as the stationary point of an appropriate functional. The final chapter deals with the solution of the Boltzmann transport equation. This book is a valuable resource for engineers.

Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory

Publications, Reports, and Papers for 1961- from Oak Ridge National Laboratory PDF Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 304

Book Description


Engineering Compendium on Radiation Shielding: Shielding fundamentals and methods

Engineering Compendium on Radiation Shielding: Shielding fundamentals and methods PDF Author:
Publisher:
ISBN:
Category : Shielding (Radiation)
Languages : en
Pages : 570

Book Description