Add to ORKGThe calculation of resonance shielding by the subgroup method as incorporated in the MIRANDA module of the AUS neutronics code system is compared with Monte Carlo calculatons for a number of thermal reactor lattices. For the large range of single rod and rod cluster lattices considered AUS results for resonance absorption were high by up to two per cent
Originally presented as the first author's thesis, (Ph. D.)--in the M.I.T. Dept. of Nuclear Engineer...
Abstract Cross section data in the resolved and unresolved resonance region are represented by nuc...
Neutronics computations are widely used in reactor physics and criticality calculations to ensure th...
MCRP is a Monte Carlo computer program for tracking neutrons slowing down in single rod and rod clu...
This paper discusses the mathematical models and methods used for calculating resonance cross sectio...
MIRANDA is the cross-section generation module of the AUS neutronics code system used to prepare mu...
The AUS modular code scheme for reactor neutronics computations has been extended to apply to fusion...
This paper reports on the development and verification of three new resonance self-shielding methods...
Details of the resonance theory used in the code GYMEA are described and compared with exact solutio...
The "Atlas of Neutron Resonances" provides detailed information on neutron resonances, thermal neutr...
Multigroup calculations of resonance neutron capture in thick slab of depleted U-23
The neutron flux in the region of, and beJow a resonance is considered. The results of Goldstein whi...
The effects of accurate modeling of neutron scattering in 238U resonances are analyzed for typical l...
A 4-energy multigroup calculation of neutron reaction rates for absorption, fission,n*fission nuclea...
This document presents the statistical description of neutron cross sections in the unresolved reson...
Originally presented as the first author's thesis, (Ph. D.)--in the M.I.T. Dept. of Nuclear Engineer...
Abstract Cross section data in the resolved and unresolved resonance region are represented by nuc...
Neutronics computations are widely used in reactor physics and criticality calculations to ensure th...
MCRP is a Monte Carlo computer program for tracking neutrons slowing down in single rod and rod clu...
This paper discusses the mathematical models and methods used for calculating resonance cross sectio...
MIRANDA is the cross-section generation module of the AUS neutronics code system used to prepare mu...
The AUS modular code scheme for reactor neutronics computations has been extended to apply to fusion...
This paper reports on the development and verification of three new resonance self-shielding methods...
Details of the resonance theory used in the code GYMEA are described and compared with exact solutio...
The "Atlas of Neutron Resonances" provides detailed information on neutron resonances, thermal neutr...
Multigroup calculations of resonance neutron capture in thick slab of depleted U-23
The neutron flux in the region of, and beJow a resonance is considered. The results of Goldstein whi...
The effects of accurate modeling of neutron scattering in 238U resonances are analyzed for typical l...
A 4-energy multigroup calculation of neutron reaction rates for absorption, fission,n*fission nuclea...
This document presents the statistical description of neutron cross sections in the unresolved reson...
Originally presented as the first author's thesis, (Ph. D.)--in the M.I.T. Dept. of Nuclear Engineer...
Abstract Cross section data in the resolved and unresolved resonance region are represented by nuc...
Neutronics computations are widely used in reactor physics and criticality calculations to ensure th...