A new and highly effective procedure for generating fission product cross sections for LMFBR studies has been developed. The resultant simplified cross sections agree with more detailed treatments to within a few percent, and thus, are particularly valuable for fuel cycle and other studies. The proposed model consists of a two-lump fission product set, one based on the odd-A fission products and the other based on the even-A fission products with transmutation between the odd and even-A isotopes through capture. To examine the behavior of the proposed odd-even model, a detailed burnup analysis of 181 fission product elements in 84 chains was performed using the fission product code EPRI-CINDER. A 154-group fission product cross-section libr...
The present work concerns two successful models used today: Point by Point (PbP) and the Monte Carlo...
In recent years the measurement of prompt fission gamma-ray spectra (PFGS) has gained renewed intere...
With the advent of increasing reactor lifetimes, the need for an accurate description of all fission...
The Fast Mixed-Spectrum Reactor (FMSR) concept has been proposed by BNL as a means of alleviating ce...
The objective of this project has been the production of a data library suitable for calculating the...
Neutron cross sections for fission products play an important role not only in the design of extende...
Abstract:. The new MultiConfiguration Fission (MCF) approach is used for calculations of nucleon ind...
Neutron cross sections for fission products play an important role not only in the design of extende...
Neutron cross sections for fission products play important role not only in the design of extended b...
Fast neutron reactors, as a possible future solution on energy demand of human society, based on fis...
This paper reports on revised cross-section evaluations for {sup 134}Ba, {sup 149}Sm, {sup 154}Eu, {...
Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files....
Abstract. Fission Cross Sections for a complete set of Cm-isotopes, 240−250Cm, have been calculated ...
Fast neutron reactors, as a possible future solution on energy demand of human society, based on fis...
Fission Cross Sections for a complete set of Cm-isotopes, 240-250Cm, have been calculated ...
The present work concerns two successful models used today: Point by Point (PbP) and the Monte Carlo...
In recent years the measurement of prompt fission gamma-ray spectra (PFGS) has gained renewed intere...
With the advent of increasing reactor lifetimes, the need for an accurate description of all fission...
The Fast Mixed-Spectrum Reactor (FMSR) concept has been proposed by BNL as a means of alleviating ce...
The objective of this project has been the production of a data library suitable for calculating the...
Neutron cross sections for fission products play an important role not only in the design of extende...
Abstract:. The new MultiConfiguration Fission (MCF) approach is used for calculations of nucleon ind...
Neutron cross sections for fission products play an important role not only in the design of extende...
Neutron cross sections for fission products play important role not only in the design of extended b...
Fast neutron reactors, as a possible future solution on energy demand of human society, based on fis...
This paper reports on revised cross-section evaluations for {sup 134}Ba, {sup 149}Sm, {sup 154}Eu, {...
Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files....
Abstract. Fission Cross Sections for a complete set of Cm-isotopes, 240−250Cm, have been calculated ...
Fast neutron reactors, as a possible future solution on energy demand of human society, based on fis...
Fission Cross Sections for a complete set of Cm-isotopes, 240-250Cm, have been calculated ...
The present work concerns two successful models used today: Point by Point (PbP) and the Monte Carlo...
In recent years the measurement of prompt fission gamma-ray spectra (PFGS) has gained renewed intere...
With the advent of increasing reactor lifetimes, the need for an accurate description of all fission...