Comparison between TORT and MCNP applications for PWR vessel fluence calculations
- Empresa Nacional del Uranio, S.A., Madrid (Spain); and others
A comparison is presented on the nodal contribution to fast neutron fluence on the vessel of a Westinghouse three-loop pressurized water reactor. The main calculations were performed with the Oak Ridge National Laboratory three-dimensional discrete ordinates transport code TORT, and a wide comparison was performed with the Los Alamos National Laboratory (LANL) continuous-energy Monte Carlo code MCNP4A. Nine light water reactors are currently in operation in Spain., five of them with the same Westinghouse three-loop design. ENUSA is the fuel supplier to these units, performing the loading pattern search and reload safety analysis. ENUSA developed this process to determine the individual contribution of each fuel assembly power to the fast neutron flux in the vessel so that the contribution to the vessel fluence in the choice of the loading pattern could be determined. The idea was to enrich the amount of information required by the utility for such a choice by means of a quick calculation of the estimated fluence contribution during the development of the preliminary loading pattern through the use of polynomial expressions of fast flux at each angle per unit relative power in the four quarters of every fuel assembly.
- OSTI ID:
- 552566
- Report Number(s):
- CONF-971125--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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