Abstract
In this paper, typical 1000-1200 MW(e) fast-reactor systems of about 6000-7000 litre core modelling - the target fast reactors being designed today by the major countries having an active fast reactor program - are calculated using the evaluated nuclear data files ENDF/B III and KEDAK as nuclear input. Identical techniques are used to obtain multigroup sets from the files. Also the reactor physics codes used are the same. The differences in results can, therefore, be attributed directly to the differences in the nuclear data input. Practical conclusions and recommendations are presented.
| Original language | English |
|---|---|
| Pages | 75-82 |
| Number of pages | 8 |
| State | Published - 1 Jan 1973 |
| Event | Nucl Data in Sci and Technol, Symp, Proc, Pap - Paris, Fr Duration: 12 Mar 1973 → 16 Mar 1973 |
Conference
| Conference | Nucl Data in Sci and Technol, Symp, Proc, Pap |
|---|---|
| City | Paris, Fr |
| Period | 12/03/73 → 16/03/73 |
ASJC Scopus subject areas
- General Engineering