Abstract
Nuclear criticality safety analyses require the utilization of methods which have been tested and verified against benchmarks results. In this work, criticality calculations based on the KENO-IV and MCNP codes are studied aiming the qualification of these methods at the IPEN-CNEN/SP and COPESP. The utilization of variance reduction techniques is important to reduce the computer execution time, and several of them are analysed. As practical example of the above methods, a criticality safety analysis for the storage tubes for irradiated fuel elements from the IEA-R1 research has been carried out. This analysis showed that the MCNP code is more adequate for problems with complex geometries, and the KENO-IV code shows conservative results when it is not used the generalized geometry option. (author).
Citation Formats
Maragni, M G.
Computational methods for nuclear criticality safety analysis; Metodos computacionais para a analise de problemas de criticalidade nuclear.
Brazil: N. p.,
1992.
Web.
Maragni, M G.
Computational methods for nuclear criticality safety analysis; Metodos computacionais para a analise de problemas de criticalidade nuclear.
Brazil.
Maragni, M G.
1992.
"Computational methods for nuclear criticality safety analysis; Metodos computacionais para a analise de problemas de criticalidade nuclear."
Brazil.
@misc{etde_10125412,
title = {Computational methods for nuclear criticality safety analysis; Metodos computacionais para a analise de problemas de criticalidade nuclear}
author = {Maragni, M G}
abstractNote = {Nuclear criticality safety analyses require the utilization of methods which have been tested and verified against benchmarks results. In this work, criticality calculations based on the KENO-IV and MCNP codes are studied aiming the qualification of these methods at the IPEN-CNEN/SP and COPESP. The utilization of variance reduction techniques is important to reduce the computer execution time, and several of them are analysed. As practical example of the above methods, a criticality safety analysis for the storage tubes for irradiated fuel elements from the IEA-R1 research has been carried out. This analysis showed that the MCNP code is more adequate for problems with complex geometries, and the KENO-IV code shows conservative results when it is not used the generalized geometry option. (author).}
place = {Brazil}
year = {1992}
month = {Dec}
}
title = {Computational methods for nuclear criticality safety analysis; Metodos computacionais para a analise de problemas de criticalidade nuclear}
author = {Maragni, M G}
abstractNote = {Nuclear criticality safety analyses require the utilization of methods which have been tested and verified against benchmarks results. In this work, criticality calculations based on the KENO-IV and MCNP codes are studied aiming the qualification of these methods at the IPEN-CNEN/SP and COPESP. The utilization of variance reduction techniques is important to reduce the computer execution time, and several of them are analysed. As practical example of the above methods, a criticality safety analysis for the storage tubes for irradiated fuel elements from the IEA-R1 research has been carried out. This analysis showed that the MCNP code is more adequate for problems with complex geometries, and the KENO-IV code shows conservative results when it is not used the generalized geometry option. (author).}
place = {Brazil}
year = {1992}
month = {Dec}
}