Multigroup versus continuous-energy MCNP for PWR fluence calculations
To ensure integrity of reactor pressure vessels and plant life extension, the neurton fluence of the pressure vessel needs to be accurately determined. A Monte Carlo method, which offers 3-D geometric representation and angular simulation, is described for this task.It is concluded that the flux distributions and cavity dosimeter activities predicted via the 3-D synthesized multigroup S{sub n} transport calculations are within 10% of the multigroup MCNP results. While these calculations clearly demonstrate the effect of the multigroup libraries, they do not, however, conclusively reveal the origin of the effect (i.e., P{sub 3} truncation, group structure, or both). Also, it is demonstrated that different multigroup libraries including SAILOR, BUGLE-80, and ELXSIR show close agreement. Future work will examine the effects of the P{sub 3} truncation and group structure.
- OSTI ID:
- 76108
- Report Number(s):
- CONF-940602--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 70; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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