Neutron Flux Characterization for Radioisotope Production at ETRR-2

The thermal, epithermal and fast fluxes were calculated for three irradiation channels at Egypt Second Research Reactor (ETRR-2) using CITVAP code. The validity of the calculations was verified by experimental measurements. There are some deviations between measurements and calculations. This is due to approximations in the calculation models used, homogenization of regions, condensation of energy groups and uncertainty in nuclear data used. Neutron flux data for the three irradiation channels are now available. This would enable predicting the irradiation conditions needed for future radioisotope production.

Authors:

• A. M. Hassanain
• Nader M. A. Mohamed
• M. Naguib Aly
• Alya A. Badawi
• M. A. Gaheen

Keywords:

• ETRR-2
• Neutron flux
• Radioisotope production
• CITVAP

References:

[1] O. Villarino, E., 1993. Initial Report Database. 0767 0700-3TANU-135-
2A.ETRR-2 Detailed Engineering.
[2] INVAP SE, 1997. Safety Analysis Report of the MPR
Reactor,Argentina, 0767-5325- 3IBLI 001-1O.
[3] Manual Of Radioisotope Production, International Atomic Energy
Agency, Vienna, 2003.
[4] A. M. Hassanain , Nader M. A. Mohamed , M. Naguib Ali , Alya
A.Badawi and M. A. Gaheen, "Measurements of thermal and epithermal
neutron fluxes for Radioisotopes production at Research
Reactors",Proceedings of the 1st International Nuclear and Renewable
Energy Conference (INREC10), Amman, Jordan, March 21-24, 2010.
[5] Askew, J.R., 1966. A General Description of the Lattice Code WIMS,
pp. 564-589, JBNES7.
[6] INVAP SE, 1993. POS-WIMS. MTR-PC User Manual, Argentina.
[7] INVAP SE, 1995. CITVAP3.1. MTR-PC User Manual, Argentina.