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[en] Neutron flux, neutron exposure rate and iron displacement cross-section averaged over the neutron spectrum in a two-loop, 632 MWe PWR were calculated. The transport code DOT 3.5 was used. Calculations were performed separately for the reactor and the surveillance capsule. Presented are spatial distributions as well as absolute values at most important locations within the capsule and the pressure vessel for BOL and EOL of the first fuel cycle. (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; 2 v. 1082 p; ISBN 90-277-2013-4; 
; 1984; p. 79-85; D. Reidel; Dordrecht (Netherlands); 5. ASTM-Euratom symposium on reactor dosimetry; Geesthacht (Germany, F.R.); 24-28 Sep 1984; 4 refs.; 4 figs.; 1 table.
; 1984; p. 79-85; D. Reidel; Dordrecht (Netherlands); 5. ASTM-Euratom symposium on reactor dosimetry; Geesthacht (Germany, F.R.); 24-28 Sep 1984; 4 refs.; 4 figs.; 1 table.