Approximate calculation of isotope ratio of a fast breeder reactor under self-sustaining mode of operation
Creators
Description
The iteration method of isotope ratio calculations for a fast breeder type reactor under self-sustaining mode of operation, assuming the linear dependence of plutonium concentration on time and considering the reactor batch loading, is described. The results of calculation of the proper plutonium isotope ratio for the fast breeder reactor on dissociating N2O4 coolant are given. The method is intended for calculation of isotope ratio of the fast breeder type reactor with the batch loading taking into account the burnup in the reactor core and plutonium generating in the screens. The method uses the results of critical base version calculated on arbitrary isotope ratio of plutonium. Testing of this method shows its convergence and agreement with estimated data. The method has been verified by the direct calculation following SINVAR-2 program
Additional details
Additional titles
- Original title (Russian)
- Приближенный расчет изотопного состава быстрого реактора-бридера в собственном режиме работы
Publishing Information
- Journal Title
- Vestsi Akad. Navuk BSSR, Ser. Fiz.-Ehnerg. Navuk
- Journal Issue
- no.2
- Series
- Vestsi Akad. Navuk BSSR, Ser. Fiz.-Ehnerg. Navuk.
- CODEN
- VAFEA
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 18014685
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BATCH LOADING; COOLANTS; DISSOCIATING GASES; FBR TYPE REACTORS; ISOTOPE RATIO; MATHEMATICAL MODELS; NITROGEN OXIDES; PLUTONIUM; S CODES
- Descriptors DEC
- ACTINIDES; BREEDER REACTORS; CHALCOGENIDES; COMPUTER CODES; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FLUIDS; GASES; METALS; NITROGEN COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; REACTOR FUELING; REACTORS; TRANSURANIUM ELEMENTS