Monte Carlo calculations on transmutation of plutonium and minor actinides of pebble bed high temperature reactor
The paper aimed to maximize the fuel burnup performance of plutonium and minor actinides fueled pebble bed high temperature reactor (PBMR-400). The PBMR-400 was designed as a reference core. The neutronic calculations were performed by the code combination MCNP-ORIGEN-MONTEBURNS. In this study, neut...
Gespeichert in:
Veröffentlicht in: | Progress in nuclear energy (New series) 2015-01, Vol.78, p.380-387 |
---|---|
Hauptverfasser: | , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
Zusammenfassung: | The paper aimed to maximize the fuel burnup performance of plutonium and minor actinides fueled pebble bed high temperature reactor (PBMR-400). The PBMR-400 was designed as a reference core. The neutronic calculations were performed by the code combination MCNP-ORIGEN-MONTEBURNS. In this study, neutronic performances of three different types of nuclear fuels (Reactor Grade Plutonium – RGPu; Weapon Grade Plutonium – WGPu and Minor Actinides – MAs) combined with natural uranium were conducted in a PBMR-400 full core. The neutronic performances were compared with the original uranium fuel designed for this reactor. Neutronic calculations showed that 9.6 wt % enriched uranium has a core effective multiplication factor (keff) of 1.2395. Corresponding to this keff values the natural UO2/RG-PuO2; natural UO2/WG-PuO2 and natural UO2/MAO2 mixture were found 70%/30%, 76%/24% and 63%/37%, respectively. The operation times were computed as ∼2000, ∼2500 and 1400 days whereas, the corresponding burnup values were obtained as ∼163 000, ∼194 000 and ∼116 000 MWD/T, respectively, for end of life keff set equal to 1.08.
•The neutronic calculations are performed by MCNP-ORIGEN-MONTEBURNS.•Neutronic properties for alternative fuels have been studied.•The plutonium and minor actinides can be transmuted in High temperature reactor. |
---|---|
ISSN: | 0149-1970 |
DOI: | 10.1016/j.pnucene.2013.11.009 |