We investigate the use of evaluated cross section data to define the nonelastic interaction rate for reactions described by the intranuclear cascade code in LAHET. We find that improved predictions of total neutron production within stopping-length target assemblies are obtained
An experiment conducted at the Los Alamos Neutron Science Center in November 1995 was used to benchm...
This chapter describes the current status of evaluated nuclear data for nuclear technology applicati...
Current trend in nuclear reactor physics is a transition from technologies using thermal neutrons to...
The intranuclear cascade (INC) code of Bruyères-le-Châtel named BRIC is the first part of the nonela...
The intranuclear cascade (INC) code of Bruyères-le-Châtel named BRIC is the first part of the nonela...
Abstract. The intranuclear cascade (INC) code of Bruyères-le-Châtel named BRIC is the first part o...
There has been considerable interest in improving the fission models in the LAHET Monte Carlo code f...
Current trend in nuclear reactor physics is a transition from technologies using thermal neutrons to...
The LAHET Monte Carlo code for the transport and interaction of nucleons, pions, muons, light ions, ...
Current trend in nuclear reactor physics is a transition from technologies using thermal neutrons to...
A recent renascent interest in energetic proton-induced production of neutrons originates largely fr...
MCNP{trademark} and LAHET{trademark} are two of the codes included in the LARAMIE (Los Alamos Radiat...
Evaluated nuclear data rather than raw experimental and theoretical information are employed in nucl...
Evaluated nuclear data rather than raw experimental and theoretical information are employed in nucl...
Evaluated nuclear data rather than raw experimental and theoretical information are employed in nucl...
An experiment conducted at the Los Alamos Neutron Science Center in November 1995 was used to benchm...
This chapter describes the current status of evaluated nuclear data for nuclear technology applicati...
Current trend in nuclear reactor physics is a transition from technologies using thermal neutrons to...
The intranuclear cascade (INC) code of Bruyères-le-Châtel named BRIC is the first part of the nonela...
The intranuclear cascade (INC) code of Bruyères-le-Châtel named BRIC is the first part of the nonela...
Abstract. The intranuclear cascade (INC) code of Bruyères-le-Châtel named BRIC is the first part o...
There has been considerable interest in improving the fission models in the LAHET Monte Carlo code f...
Current trend in nuclear reactor physics is a transition from technologies using thermal neutrons to...
The LAHET Monte Carlo code for the transport and interaction of nucleons, pions, muons, light ions, ...
Current trend in nuclear reactor physics is a transition from technologies using thermal neutrons to...
A recent renascent interest in energetic proton-induced production of neutrons originates largely fr...
MCNP{trademark} and LAHET{trademark} are two of the codes included in the LARAMIE (Los Alamos Radiat...
Evaluated nuclear data rather than raw experimental and theoretical information are employed in nucl...
Evaluated nuclear data rather than raw experimental and theoretical information are employed in nucl...
Evaluated nuclear data rather than raw experimental and theoretical information are employed in nucl...
An experiment conducted at the Los Alamos Neutron Science Center in November 1995 was used to benchm...
This chapter describes the current status of evaluated nuclear data for nuclear technology applicati...
Current trend in nuclear reactor physics is a transition from technologies using thermal neutrons to...
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