Irradiation behaviour of ferroboron – An alternate in-core shielding material for sodium-cooled fast reactors
| Autor: | M. Padalakshmi, C.N. Venkiteswaran, B.K. Ojha, V. Anandaraj, R. Divakar, C. Padmaprabu, A. Vijayaragavan, Ran Vijay Kumar, V.V. Jayaraj, Bhabani Shankar Dash, V. Karthik |
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| Rok vydání: | 2021 |
| Předmět: |
Nuclear and High Energy Physics
Materials science 020209 energy Mechanical Engineering Nuclear engineering chemistry.chemical_element 02 engineering and technology Neutron radiation 01 natural sciences 010305 fluids & plasmas Breeder (animal) Nuclear Energy and Engineering chemistry Neutron flux 0103 physical sciences Electromagnetic shielding 0202 electrical engineering electronic engineering information engineering General Materials Science Neutron Lithium Irradiation Safety Risk Reliability and Quality Waste Management and Disposal Helium |
| Zdroj: | Nuclear Engineering and Design. 377:111126 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/j.nucengdes.2021.111126 |
| Popis: | Fast reactor cores employ a large number of sub-assemblies for neutron and gamma shielding constituting more than 60% of the core volume. Use of effective and economical shielding materials can significantly improve the safety and cost competitiveness of fast reactors. Ferroboron has been identified as an efficient neutron shielding material for deployment in future commercial breeder reactors in India that can lead to significant cost savings. After successful shielding experiments and out-of-pile compatibility tests, a SS 304L clad irradiation capsule containing ferroboron powder has been subjected to an accelerated irradiation test in Fast Breeder Test Reactor (FBTR) to a peak neutron fluence of 8.18E21 n/cm2 for evaluating its in-reactor performance. Results of Post Irradiation Examinations carried out on the irradiation capsule to assess the various performance parameters such as slumping of ferroboron stack, helium release and chemical interaction of SS 304L with ferroboron are reported here. The examinations have indicated that extent of slumping is less than 1% and pressure build up due to helium release is 0.17 MPa (at room temperature), which are well within the permissible limits. A maximum clad wastage of 20% of wall thickness has been observed due to chemical interaction with lithium produced from (n,α) reaction. The irradiation performance assessment of ferroboron indicates its suitability for in-core shielding application in fast reactors. |
| Databáze: | OpenAIRE |
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