MCNPX Modeling of BN-600 Full MOX Fast Reactor Core
The BN-600 full mixed oxide fueled core is modeled using MCNPX code. A three dimensional model typical of the core is prepared which includes 6 radial zones, low enrichment zone, medium enrichment zone and high enrichment zone, two zones of steel shielding assemblies, and a radial blanket in additio...
Gespeichert in:
Veröffentlicht in: | 材料科学与工程:中英文B版 2013, Vol.3 (8), p.530-534 |
---|---|
1. Verfasser: | |
Format: | Artikel |
Sprache: | chi |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
Zusammenfassung: | The BN-600 full mixed oxide fueled core is modeled using MCNPX code. A three dimensional model typical of the core is prepared which includes 6 radial zones, low enrichment zone, medium enrichment zone and high enrichment zone, two zones of steel shielding assemblies, and a radial blanket in addition to shim and scram rods. The twelve axial zones are also modeled. The model calculates core parameters such as reactor multiplication factor, power distribution through reactor core, and control rod worth. An estimation of isotope transmutation through various reactor zones and analysis of internal breeding zone were presented. The results are compared with previously published results which indicated good agreement. Typical results of the present model for reactor multiplication factor are !.00832 compared with transport model (1.00664) and diffusion model (1.00131). The high enrichment zone dominates power production. The results also estimate the isotope variation due to burnup in the MOX core. |
---|---|
ISSN: | 2161-6221 |