| Zugriffsnummer | 30898 |
| Dokumenttyp | Konferenzartikel in Zeitschrift |
| Sprache | Englisch |
| Titel | Simulation of neutron production using MCNPX + MCUNED |
| Autor(in); Institution |
Erhard, Martin; 6.4, Ionen- und Neutronenstrahlung, PTB-Braunschweig
Sauvan, P.; Universidad Nacional de Educación a Distancia (UNED), Departamento de Ingeniería Energética, Madrid, SPAIN
Nolte, Ralf; 6.4, Ionen- und Neutronenstrahlung, PTB-Braunschweig
|
| Quelle/Jahr | Radiation Protection Dosimetry: 161 (2014), 1/4, 261 - 264 |
| ISSN | 0144-8420 (PRINT) ; 1742-3406 (ONLINE) |
| DOI | |
| Verlag | Oxford: Oxford University Press |
| Konferenzangaben | Neutron and Ion Dosimetry Symposium, Aix-en-Provence, 03-07, June, 2013, France |
| Zusammenfassung | In standard MCNPX, the production of neutrons by ions cannot be modelled efficiently. The MCUNED patch applied to MCNPX 2.7.0 allows to model the production of neutrons by light ions down to energies of a few kiloelectron volts. This is crucial for the simulation of neutron reference fields. The influence of target properties, such as the diffusion of reactive isotopes into the target backing or the effect of energy and angular straggling, can be studied efficiently. In this work, MCNPX/MCUNED calculations are compared with results obtained with the TARGET code for simulating neutron production. Furthermore, MCUNED incorporates more effective variance reduction techniques and a coincidence counting tally. This allows the simulation of a TCAP experiment being developed at PTB. In this experiment, 14.7-MeV neutrons will be produced by the reaction T(d,n)4He. The neutron fluence is determined by counting alpha particles, independently of the reaction cross section. |
