Abstract

Boron, Titanium and boron – titaniumaustenitic stainless steel alloys were developed to be used as a nuclear reactor shielding material. Three grades of steel alloys with base composition of AISI316 but having either Ti or B or Ti and B (SS316Ti, SS316B and SS316TiB) were designed and produced using 30 kg pilot plant medium frequency induction furnace at the same conditions. Samples of the properly treated steels were subjected to microstructure observation, hardness, tensile and impact testing. The microstructure observation revealed an austenitic phase in all investigated steel alloys. Among the investigated steels, the lowest corrosion rate was found in the modified steel containing B. The macroscopic-cross sections for neutrons > 10 keV, slow, and total slow neutrons were carried out using 241Am-Be neutron source. The developed boron and boron-titanium stainless steel alloys were found to have higher cross sections for neutrons > 10 keV, slow, and total slow neutrons than SS316 while the modified Ti- stainless steel has lower values for slow neutrons and neutrons > 10 keV than the standard stainless steel SS316. Moreover, the associated neutron half value layer (HVL) was calculated for each sample. Additionally, gamma ray shielding properties were performed for several gamma ray energies that emitted from 232Th radioactive source.

Highlights

  • In recent years, the demand for various absorption materials has been increased in nuclear industry to ensure safety in disposal of spent fuel

  • Borated stainless steels were used to control neutron flux in reactors, transportation casks and spent fuel pool storage racks over thirty years ago [4]. These materials were characterized as having ductility and impact resistance below what was considered acceptable for structural materials

  • The higher B content accelerates the formation of intermetallic compounds and lowers the ductility

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Summary

Introduction

The demand for various absorption materials has been increased in nuclear industry to ensure safety in disposal of spent fuel. Out of various neutron absorption materials, those containing boron (10B) were more preferred in nuclear industry due to their low cost and very high. Borated stainless steels were used to control neutron flux in reactors, transportation casks and spent fuel pool storage racks over thirty years ago [4]. These materials were characterized as having ductility and impact resistance below what was considered acceptable for structural materials. Borated stainless steel that possesses both neutron attenuation properties as well as adequate ductility and impact resistance is preferred to be used as a structural material that offers obvious advantage and is highly desirable [6]

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