NSUF 24-4970: Testing purity of molten salts – neutron activation analysis study

Molten salt reactors (MSR) are one of the most promising advanced nuclear reactors which are expected to significantly contribute both to energy production and to closing nuclear fuel cycle in the future. Various chloride salts are considered for fast MSRs, while fluoride salts are usually employed for thermal MSRs. Significant efforts have been made to synthesize pure fluoride or chloride molten salts and synthesis requires high temperatures (more than 500 °C) and an oxygen free atmosphere. Rigorous purity requirements are imposed on the synthesized molten salts. This is because even a trace impurity can cause additional corrosion (especially oxygen containing impurities) and will be activated during reactor operation. Proposed work aims to perform neutron activation analysis of the various molten salts considered for the application in thermal and fast MSR. For this purpose, small samples of several molten salt candidates will be irradiated in the Breazeale Nuclear Research Reactor of the Pennsylvania State University (PSBR). Irradiated samples will be measured using HPGe detector equipped with the Compton Suppression System and measured spectra will be analyzed to identify activation products and impurities. Such a neutron activation analysis study could improve our understanding of radiation levels from major and minor elements from the molten salt candidate materials and possibly create a basis for future quality control of various molten salts.

추가 정보

필드	값
Award Announced Date	2024-05-28T17:10:33.95
Awarded Institution	Pennsylvania State University
Facility Tech Lead
Irradiation Facility
PI	Artem Matyskin
PI Email	[email protected]
Project Type	RTE
RTE Number	None