Neutron cross sections for fission products play important role not only in the design of extended burnup core and fast reactors, but also in the study of the backend fuel cycle and the criticality analysis of spent fuel. New evaluations in both the resonance and fast neutron regions were performed by the KAERI-BNL collaboration for 32 fission products. These were {sup 95}Mo, {sup 101}Ru, {sup 103}Rh, {sup 105}Pd, {sup 109}Ag, {sup 131}Xe, {sup 133}Cs, {sup 141}Pr, and complete isotope chains of {sup 142-148,150}Nd, {sup 144,147,148-154}Sm, and {sup 156,158,160-164}Dy. The evaluations cover a large amount of reaction channels, including all those needed for neutronics calculations. Also, they cover the entire energy range, from 10{sup -5} e...
We describe the new ENDF/B-VIII.0 evaluated nuclear reaction data library. ENDF/B-VIII.0 fully incor...
A sensitivity analysis for the new generation of fast reactors [Salvatores (2008)] has shown the imp...
A new and highly effective procedure for generating fission product cross sections for LMFBR studies...
Neutron cross sections for fission products play an important role not only in the design of extende...
Neutron cross sections for fission products play an important role not only in the design of extende...
The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear sc...
Neutron cross sections for a complete set of Nd isotopes, {sup 142,143,144,145,146,147,148,150}Nd, w...
Neutron cross section evaluations of the fission-product isotopes, {sup 95}Mo, {sup 99}Tc, {sup 101}...
We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recomm...
This paper reports on revised cross-section evaluations for {sup 134}Ba, {sup 149}Sm, {sup 154}Eu, {...
A sensitivity analysis for the new generation of fast reactors [Salvatores (2008)] has shown the imp...
With the need for improving existing nuclear data evaluations, (e.g., ENDF/B-VIII.0 and JEFF-3.3 rel...
A sensitivity analysis for the new generation of fast reactors [Salvatores (2008)] has shown the imp...
Recent extensions and improvements of the EMPIRE code system are outlined. They add new capabilities...
Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files....
We describe the new ENDF/B-VIII.0 evaluated nuclear reaction data library. ENDF/B-VIII.0 fully incor...
A sensitivity analysis for the new generation of fast reactors [Salvatores (2008)] has shown the imp...
A new and highly effective procedure for generating fission product cross sections for LMFBR studies...
Neutron cross sections for fission products play an important role not only in the design of extende...
Neutron cross sections for fission products play an important role not only in the design of extende...
The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear sc...
Neutron cross sections for a complete set of Nd isotopes, {sup 142,143,144,145,146,147,148,150}Nd, w...
Neutron cross section evaluations of the fission-product isotopes, {sup 95}Mo, {sup 99}Tc, {sup 101}...
We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recomm...
This paper reports on revised cross-section evaluations for {sup 134}Ba, {sup 149}Sm, {sup 154}Eu, {...
A sensitivity analysis for the new generation of fast reactors [Salvatores (2008)] has shown the imp...
With the need for improving existing nuclear data evaluations, (e.g., ENDF/B-VIII.0 and JEFF-3.3 rel...
A sensitivity analysis for the new generation of fast reactors [Salvatores (2008)] has shown the imp...
Recent extensions and improvements of the EMPIRE code system are outlined. They add new capabilities...
Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files....
We describe the new ENDF/B-VIII.0 evaluated nuclear reaction data library. ENDF/B-VIII.0 fully incor...
A sensitivity analysis for the new generation of fast reactors [Salvatores (2008)] has shown the imp...
A new and highly effective procedure for generating fission product cross sections for LMFBR studies...