The effect of random geometry on the criticality of a multiplying system III: Three dimensional systems and spherical absorbers

Nuclear Science and Engineering

Volumn 141, Issue 1, 2002, Pages 13-31

  Williams, M M R ^a  

^a NONE   (United Kingdom)

Author keywords

[No Author keywords available]

Indexed keywords

ANISOTROPY; GEOMETRY; GREEN'S FUNCTION; NUCLEAR FUEL ELEMENTS; NUCLEAR REACTORS; PROBABILITY DISTRIBUTIONS; RADIOACTIVE WASTES;

FISSILE MATERIALS;

NEUTRONS;

EID: 0036567771     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE02-A2263     Document Type: Article

References (33)

1. The effect of random geometry on the criticality of a multiplying system
2. The effect of random geometry on the criticality of a multiplying system II: Extension to resonance absorption
3. On galanin's constant in the source-sink method
4. On the definition of the extrapolated surface for bare homogeneous thermal reactors
5. On a probability distribution function arising in stochastic neutron transport theory
6. Stochastic equations and wave propagation in random media
7. Neutron transfer theory for inhomogeneous media
8. Reactivity effects and space domain noise caused by randomly dispersed materials in a reactor core
9. Reactivity effects and flux perturbations due to spatial random dispersal in the number densities of core materials
10. Analysis of the reactivity effect of spatial noise in the framework of two-group diffusion theory
11. Application of the theory of random matrices to a reactor noise problem
12. Probability distributions for first neighbour distance between resonances that belong to two different families
13. Neutron transport in spatially random media: An assessment of the accuracy of first order smoothing
14. Neutron transport in spatially random media: Eigenvalue problems
15. On the natural frequencies of a disordered linear chain of N degrees of freedom
16. The interaction effect between two neutron absorbers using wallace's method
17. Transport theory corrections to the source-sink method for reactor lattice calculations
18. Heterogeneous theory of finite reflected lattices 1. Two-dimensional multigroup theory with one thermal group and flux independent cross section
19. A study of approximate methods for calculating the neutron flux in a heterogeneous reactor