Author: S. Wallach
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 64
Book Description
In this report the problem is considered of determining neutron flux distributions in reactors consisting of discrete regions of substantially different nuclear properties. Starting with these equations the problem is considered of determining the flux in one of the energy groups given the spatial flux distribution of the next higher energy group. The problem is handled by converting the differential equation with source term to an integral equation; under appropriate conditions the integral equation may be solved by a numerical iterative procedure. The conditions under which this may be done are discussed and formulas are developed for placing bounds on the errors. In addition the technique of obtaining flux distributions in complicated configurations by additive and multiplicative superposition of flux distributions of simpler configurations is considered. Expressions are derived for estimating the errors made in using these methods. A number of simple examples are presented.
Neutron Flux Distributions in Multiple Region Reactors
Neutron Flux Distributions in multiple region reactors
Reactivity and Neutron Flux Distribution Studies in Multi-region Loaded Reactor Cores
Author: W. J. Eich
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 506
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 506
Book Description
Neutron Flux Distributions in multiple region reactors
The Study of Multi-region Reactors with an Analog Computer
Author: J. C. Peden
Publisher:
ISBN:
Category : Analog computers
Languages : en
Pages : 116
Book Description
Publisher:
ISBN:
Category : Analog computers
Languages : en
Pages : 116
Book Description
Multi-region Reactor Lattice Studies, Quarterly Progress Report
Neutron Flux Distributions in Organic Moderated Reactor Cores
Author: V. A. Swanson
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 26
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 26
Book Description
Report on Calculations of the Neutron Flux Distribution in the Reactor Tank, the Reflectors and Thermal Column of the Uranium Pile at Kjeller
Neutron Flux Distributions in Natural Uranium Tubes
Author: Thomas B. Ponder
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 32
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 32
Book Description
Minimum Critical Mass and Uniform Thermal Neutron Core Flux in an Experimental Reactor
Author: J. W. Morfitt
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 170
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 170
Book Description