|
|
 |
| |
|
|
|
Developed Austenitic Stainless Steel Fuel Cladding for a Fast Nuclear Reactor |
|
|
|
PP: 103-113 |
|
|
|
doi:10.18576/jrna/100203
|
|
|
|
Author(s) |
|
|
|
Sara E. Saleh,
H. A. Saudi,
M. K. Elfawakhry,
S. M. El-Minyawi,
M.M. Eissa,
|
|
|
|
Abstract |
|
|
| In the present study, a series of austenitic stainless-steel alloys were developed for fuel cladding in fast breeder reactors. Standard austenitic stainless steel SS304L and SS316L were prepared and studied as a reference sample. The other samples were prepared by interchanging the molybdenum in standard SS316L with tungsten and adding titanium to the standard samples. The thermodynamic calculation was established using the JMatPro database to identify the phases that can be formed in the prepared samples. The microstructure properties of the present stainless-steel alloys were investigated using an optical microscope, Mainly, an austenite phase was observed for the prepared stainless-steel alloys. The mechanical properties of the prepared alloys were studied using Vickers hardness and tensile tests at room temperature which indicated that the modified austenitic stainless steel samples containing tungsten and titanium have preferable properties, higher hardness, yield strength, and ultimate tensile strength, among all other investigated samples in comparison with the standard SS316L and SS304L. Monte Carlo simulations program MNCP5 were used to determine the critical gamma radiation attenuation characteristics, particularly linear attenuation coefficients, mass attenuation coefficients, and half-value layer of the investigated stainless-steel alloys. Also, MNCP5 was used to calculate the Total neutron cross-section, absorption neutron cross-section, and mean free path at a high neutron energy range from about (0.5 to 11MeV). |
|
|
|
|
|
|
|
