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
The thermal-neutron fluxes in the lattice positions and selected experimental positions of the ETR w...
A gradient of neutron flux distribution in an irradiation channel in research reactor is considered ...
The result for large sample irradiation are continuously piping into the Center for Energy Research ...
International audienceReactor dosimetry techniques are commonly used for the characterization of neu...
A newly constructed remotely accessible shielded cell is available at the Missouri University of Sci...
In standardization NAA, it is necessary to characterize the neutron spectrum parameters such as epit...
A project was initiated at the Jožef Stefan Institute to develop methodology for the validation of t...
An experimental verification of Monte Carlo neutron flux calculations in typical irradiation channel...
Neutron flux of the thermal subcritical multiplication complex located at the nuclear pole of the Un...
International audienceThe National Center for Energy, Sciences and Nuclear Techniques (CNESTEN)'s Tr...
An activation-foil method was used to obtain the energy spectrum of the prompt-neutron flux at the M...
Abstract. The new Egyptian Research Reactor (ETRR-2) is a Material Testing Reactor (MTR) and it was ...
The neutron flux is a crucial parameter for the analysis of nuclear reactors, because it affects the...
The CNESTEN (National Center for Energy Sciences and Nuclear Technology, Morocco) operates a TRIGA M...
The result for large sample irradiation are continuously piping into the Center for Energy Research ...
The thermal-neutron fluxes in the lattice positions and selected experimental positions of the ETR w...
A gradient of neutron flux distribution in an irradiation channel in research reactor is considered ...
The result for large sample irradiation are continuously piping into the Center for Energy Research ...
International audienceReactor dosimetry techniques are commonly used for the characterization of neu...
A newly constructed remotely accessible shielded cell is available at the Missouri University of Sci...
In standardization NAA, it is necessary to characterize the neutron spectrum parameters such as epit...
A project was initiated at the Jožef Stefan Institute to develop methodology for the validation of t...
An experimental verification of Monte Carlo neutron flux calculations in typical irradiation channel...
Neutron flux of the thermal subcritical multiplication complex located at the nuclear pole of the Un...
International audienceThe National Center for Energy, Sciences and Nuclear Techniques (CNESTEN)'s Tr...
An activation-foil method was used to obtain the energy spectrum of the prompt-neutron flux at the M...
Abstract. The new Egyptian Research Reactor (ETRR-2) is a Material Testing Reactor (MTR) and it was ...
The neutron flux is a crucial parameter for the analysis of nuclear reactors, because it affects the...
The CNESTEN (National Center for Energy Sciences and Nuclear Technology, Morocco) operates a TRIGA M...
The result for large sample irradiation are continuously piping into the Center for Energy Research ...
The thermal-neutron fluxes in the lattice positions and selected experimental positions of the ETR w...
A gradient of neutron flux distribution in an irradiation channel in research reactor is considered ...
The result for large sample irradiation are continuously piping into the Center for Energy Research ...