A basic technique in the design of a nuclear power reactor is to prescribe the dimensions and composition of a simplified model and to calculate the corresponding neutron flux and power distributions. Comparison of calculations for different models and of particular calculations to experimental results guides the physicist to a reasonable prescription. Until recently, the usual model had spherical or cylindrical symmetry. We have found it feasible to extend the methods to include a class of reactors in which there is variation of composition with respect to two space-dimensions. In this paper, we summarize some of our experience with these calculations
The standard procedure for the calculation of neutron leakage rate of an assembly is based on calcul...
It has been suggested that a Fission-Plate Converter (FPC) at a reactor can enhance the intense of a...
This comprehensive volume offers readers a progressive and highly detailed introduction to the compl...
A basic technique in the design of a nuclear power reactor is to prescribe the dimensions and compos...
In this report the problem is considered of determining neutron flux distributions in reactors consi...
An experiment designed to measure neutron flux peaking in a reactor core due to the presence of a wa...
The primary purpose of these experiments was to measure the spatial distribution of neutron flux and...
When designing a reactor a preliminary design is done in order to obtain a rough estimate of various...
The paper considers the influence of the spatial grid type on the result of solving the equation of ...
Critical mass, fuel concentration, power, maximum power density, and wall power density were obtaine...
Calculations for one-, two-, and simulated three-dimensional cell models of a radially loaded reacto...
A number of cases were studied to determine some of the nuclear characterlstics of double-blanket re...
The purpose of this work is to present the most pertinent parts of the body of physics knowledge whi...
Thermionic reactors with U-233 as fuel and Beryllium as moderator are appropriate as primary or seco...
Modelling of nuclear reactor multi-physics: From local balance equations to macroscopic models in ne...
The standard procedure for the calculation of neutron leakage rate of an assembly is based on calcul...
It has been suggested that a Fission-Plate Converter (FPC) at a reactor can enhance the intense of a...
This comprehensive volume offers readers a progressive and highly detailed introduction to the compl...
A basic technique in the design of a nuclear power reactor is to prescribe the dimensions and compos...
In this report the problem is considered of determining neutron flux distributions in reactors consi...
An experiment designed to measure neutron flux peaking in a reactor core due to the presence of a wa...
The primary purpose of these experiments was to measure the spatial distribution of neutron flux and...
When designing a reactor a preliminary design is done in order to obtain a rough estimate of various...
The paper considers the influence of the spatial grid type on the result of solving the equation of ...
Critical mass, fuel concentration, power, maximum power density, and wall power density were obtaine...
Calculations for one-, two-, and simulated three-dimensional cell models of a radially loaded reacto...
A number of cases were studied to determine some of the nuclear characterlstics of double-blanket re...
The purpose of this work is to present the most pertinent parts of the body of physics knowledge whi...
Thermionic reactors with U-233 as fuel and Beryllium as moderator are appropriate as primary or seco...
Modelling of nuclear reactor multi-physics: From local balance equations to macroscopic models in ne...
The standard procedure for the calculation of neutron leakage rate of an assembly is based on calcul...
It has been suggested that a Fission-Plate Converter (FPC) at a reactor can enhance the intense of a...
This comprehensive volume offers readers a progressive and highly detailed introduction to the compl...