Add to ORKGFor safety studies of transmutation concepts and ADS designs, the SIMMER code is under development and extension. We present a new nuclear data processing system for SIMMER based on a recently established multigroup cross-section library processed from evaluated nuclear data files. Important features of the system are compatibility with MCNP and ERANOS and employment of a new technique, extended probability tables, for approximating resonance self-shielding of neutron cross-sections. 1
The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F a...
The NJOY Nuclear Data Processing System is used all over the world to process evaluated nuclear data...
In nuclear criticality safety applications, a number of important uncertainties have to be addressed...
International audienceCore disruptive accidents in fast reactors need to bemonitored carefully since...
The SIMMER-code family has played an outstanding role in the framework and history of mechanistic sa...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
The multi-group cross-section generation capability for neutrons is implemented in the FRENDY nuclea...
SIMMER-III and SIMMER-IV are general two-dimensional and three-dimensional, multi-velocity-field, mu...
This thesis describes a tool called TXSAMC (Transport Cross Sections from Applied Monte Carlo) that ...
An upgrade for MCNP has been implemented to sample the neutron cross sections in the unresolved reso...
Accurate neutron cross-section data is fundamental to the reliable design of any transmutation devic...
Abstract. A nuclear data library production system has been written to recover and format nuclear da...
Under the fast reactor simulation program launched in April 2007, development of an advanced multigr...
AbstractFirst priority tasks to be resolved in the development of new generation of nuclear data sup...
The nuclear research and development community has a history of using both integral and differential...
The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F a...
The NJOY Nuclear Data Processing System is used all over the world to process evaluated nuclear data...
In nuclear criticality safety applications, a number of important uncertainties have to be addressed...
International audienceCore disruptive accidents in fast reactors need to bemonitored carefully since...
The SIMMER-code family has played an outstanding role in the framework and history of mechanistic sa...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
The multi-group cross-section generation capability for neutrons is implemented in the FRENDY nuclea...
SIMMER-III and SIMMER-IV are general two-dimensional and three-dimensional, multi-velocity-field, mu...
This thesis describes a tool called TXSAMC (Transport Cross Sections from Applied Monte Carlo) that ...
An upgrade for MCNP has been implemented to sample the neutron cross sections in the unresolved reso...
Accurate neutron cross-section data is fundamental to the reliable design of any transmutation devic...
Abstract. A nuclear data library production system has been written to recover and format nuclear da...
Under the fast reactor simulation program launched in April 2007, development of an advanced multigr...
AbstractFirst priority tasks to be resolved in the development of new generation of nuclear data sup...
The nuclear research and development community has a history of using both integral and differential...
The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F a...
The NJOY Nuclear Data Processing System is used all over the world to process evaluated nuclear data...
In nuclear criticality safety applications, a number of important uncertainties have to be addressed...