Back to Search Start Over

Development of Cesium Trap Material for Coated Fuel Particles in High Temperature Gas-Cooled Reactors

Authors :
M. Goto
K. Sasaki
S. Miura
H. Ohashi
K. Fukumoto
Source :
Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics.
Publication Year :
2021
Publisher :
American Society of Mechanical Engineers, 2021.

Abstract

Cs-Bi and Cs-Sb absorbed graphite samples (Cs-Bi/graphite and Cs-Sb/graphite) were synthesized and their high temperature chemical stabilities were tested up to 1500 °C by TG and analyzed by TEM-EDS for the development of Cs trap material in high temperature gas-cooled reactor (HTGR) fuel particles. It was observed that Cs was stabilized by Sb but not by Bi in the specimens after the TG test. A rapid weight loss from 800 to 1000 °C may be caused by evaporation of Cs (boiling point: 671 °C) was seen in the TG result of both specimens. Precipitated Cs-Sb substance in the graphite matrix were not resolved even after the 1500 °C heating. The chemical composition of the Cs-Sb was specified as Cs3Sb. The experimental results suggest that Sb have potential to be a Cs getter material in graphite matrix. Long term heating test should be performed to confirm adaptability of Sb for Cs trap material in HTGR fuel particles.

Details

Database :
OpenAIRE
Journal :
Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics
Accession number :
edsair.doi...........e8ce45e0e59accf52546d2a4d59b70a5