Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.011 seconds
[en] A dosimetry irradiation was carried out at the Buffalo Reactor in order to provide exposure data under carefully controlled conditions. The data will provide a basis for correlation of calculated neutron exposure values with the experimental measurements. The dosimetry irradiation was performed in a mockup of an actual metallurgical assembly, which was carefully measured to ensure correct dimensions would be used in the calculation. The calculation was performed using transport theory and detailed estimates of fuel burnup throughout the core. Comparisons of the calculation and experimental measurements indicate good agreement and that exposure parameter values can be determined to within 10 to 15% under typical conditions. (Auth.)
Source
Genthon, J.P. (CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France)); Roettger, H. (Commission of the European Communities, Petten (Netherlands). Joint Nuclear Research Center) (eds.); Commission of the European Communities, Petten (Netherlands). Joint Nuclear Research Center; v. 1-2 1082 p; ISBN 90-277-2013-4; 
; 1984; p. 629-637; D. Reidel; Dordrecht (Netherlands); 5. ASTM-Euratom symposium on reactor dosimetry; Geesthacht (Germany, F.R.); 24-28 Sep 1984; 7 refs.; 4 figs.; 2 tabs.
; 1984; p. 629-637; D. Reidel; Dordrecht (Netherlands); 5. ASTM-Euratom symposium on reactor dosimetry; Geesthacht (Germany, F.R.); 24-28 Sep 1984; 7 refs.; 4 figs.; 2 tabs.