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 90
... pressure vessel [ 3_7 . But this could not be taken as representative for a large power reactor . So a study had been conducted for the radial shield of a large BWR ( KRB II , 1300 MWe at Gundremmingen ) and the results e e should be ...
... pressure vessel [ 3_7 . But this could not be taken as representative for a large power reactor . So a study had been conducted for the radial shield of a large BWR ( KRB II , 1300 MWe at Gundremmingen ) and the results e e should be ...
Page 90
... pressure vessel [ 3_7 . But this could not be taken as representative for a large power reactor . So a study had been conducted for the radial shield of a large BWR ( KRB II , 1300 MWe at Gundremmingen ) and the results e e should be ...
... pressure vessel [ 3_7 . But this could not be taken as representative for a large power reactor . So a study had been conducted for the radial shield of a large BWR ( KRB II , 1300 MWe at Gundremmingen ) and the results e e should be ...
Page 146
... pressure - vessel regions of a Pressurised Water Reactor . Extensive measurements were carried out and laboratories ... pressure - vessel and the influence of data uncertainties on the accuracy of calculation of the 58Ni ( n , p ) 58Co ...
... pressure - vessel regions of a Pressurised Water Reactor . Extensive measurements were carried out and laboratories ... pressure - vessel and the influence of data uncertainties on the accuracy of calculation of the 58Ni ( n , p ) 58Co ...
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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Common terms and phrases
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