Compte Rendu D'une Réunion de Spécialistes Sur Les Données Nucléaires Et Les Expériences Repères en Matière de Protection Des RéacteursNuclear Energy Agency, Organisation for Economic Co-operation and Development, 1981 - Bench-marks - 421 pages |
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Page 22
... gamma - production Pu - 241 1266 without gamma - production 25 Mn - 55 1197 Pu - 242 1161 without gamma - production ENDL - 3 results are given in Table III . Comparing the dose. Table I : Content of the coupled neutron - gamma ...
... gamma - production Pu - 241 1266 without gamma - production 25 Mn - 55 1197 Pu - 242 1161 without gamma - production ENDL - 3 results are given in Table III . Comparing the dose. Table I : Content of the coupled neutron - gamma ...
Page 91
... gamma radiation as given in Figure 10 for heating.A stronger energy peak between 6 and 8 Mev is observed in Figure 11 for the gamma dose . In the error analysis covariance matrices have been applied in the EURLIB structure for hydrogen ...
... gamma radiation as given in Figure 10 for heating.A stronger energy peak between 6 and 8 Mev is observed in Figure 11 for the gamma dose . In the error analysis covariance matrices have been applied in the EURLIB structure for hydrogen ...
Page 159
... gamma - ray produced in the iron between the graphite and the concrete region . In this sensitivity study of " JOYO ... gamma ray groups . The energy range of neutron is from 14.9MeV to thermal , and that of the gamma ray is from 14MeV ...
... gamma - ray produced in the iron between the graphite and the concrete region . In this sensitivity study of " JOYO ... gamma ray groups . The energy range of neutron is from 14.9MeV to thermal , and that of the gamma ray is from 14MeV ...
Contents
SUMMARY OF THE MEETING | 11 |
SUMMARY OF THE SESSION I | 17 |
STATUS OF MULTIGROUP CROSSSECTION LIBRARIES AVAILABLE FROM | 35 |
Copyright | |
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adjoint adjustment AMPX ANISN C. R. Weisbin Cadarache cm Acier concrete shield configuration core counter covariance matrices cross sections Cuve d'ajustement d'une détecteurs detector deux DEVIATION données de base Drischler DUCKPOND effectué effets elastic ENDF/B-IV energy group ENERGY MEV energy range error estimated été EURLIB expériences experimental fast neutron Fast Reactor Figure files fission flux fonction FORSS gamma gamma-ray group structure incertitudes integral Ispra iteration l'Acier measurements method méthode Monte Carlo Monte Carlo method multigroup neutron flux neutron groups neutron spectrum neutronique NON-ELASTIC nucléaires Nuclear Data ORNL parameters perturbation perturbation theory Physics and Shielding pressure vessel programme propagation proportional counters proton Radiation Rapport réacteurs reaction reaction-rate Reactor Physics Reactor Shielding résultats réunion RSIC SAMPO sections efficaces sensibilité sensitivity analysis Sensitivity and Uncertainty sensitivity coefficients sensitivity profiles Sensitivity Studies sodium Table TABLEAU thermal transport calculation uncertainty analysis utilisant valeurs Winfrith