Published 2017 | Version v1
Miscellaneous Open

Performance Evaluation of Ferroboron Shielding Material after Irradiation in FBTR

Description

Ferro boron has been identified as a candidate material for in-vessel radiation shielding application in future Fast Breeder Reactors (FBRs) in India that can result in significant cost savings. Out-of-pile physical and chemical characterization studies have established its neutron shielding property and long-term compatibility with 304L SS clad under sodium at the operating temperatures. An irradiation experiment was designed and carried out with the aim of establishing in-reactor performance of ferroboron shielding material over a target life-time of 60 years. This paper reports on post-irradiation examinations carried out on the experimental capsule. The results show that slumping of stack and helium release are not life limiting for deployment of ferroboron for in-core shielding in fast reactors. (author)

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Additional details

Publishing Information

Imprint Title
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers
Imprint Pagination
vp.
Journal Page Range
8 p.
Report number
IAEA-CN--245

Conference

Title
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
Acronym
FR17
Dates
26-29 Jun 2017
Place
Yekaterinburg (Russian Federation)

Optional Information

Lead record
akv0m-9ad48
Notes
5 refs., 5 figs., 4 tabs.
Secondary number(s)
IAEA-CN--245-250