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Title: Sorption of cesium by strontium-impregnated nuclear grade graphite at high temperature

Thesis/Dissertation ·
OSTI ID:5567014

Of the fission product nuclides generated in a typical high temperature gas-cooled reactor (HTGR), cesium exhibits the most complex transport behavior and is of primary interest, along with strontium, because of the health hazards associated with the potential release of /sup 137/Cs and /sup 90/Sr. Both of these elements are known to interact strongly with HTGR fuel element matrix and core structural graphites, exhibiting a Freundlich-type sorption behavior. In view of the fundamental interest and practical importance of assessing the behavior of cesium in nuclear grade graphite, the vapor pressure of cesium was determined as a function of cesium and strontium concentration in the reference nuclear graphite H-451. Cesium sorption isotherms were obtained at less than monolayer coverage using the pseudo-isopiestic method over the temperature range of 1073 to 1373 K and cesium vapor pressure range of 1 x 10/sup -4/ to 10 Pa. Cesium sorption isotherms were also obtained at 1273 K over a similar vapor pressure range for H-451 graphite diffusion-impregnated with strontium to concentrations ranging from 0.59 to 7.81 mmol Sr/kg graphite. The elements were tagged with /sup 137/Cs and /sup 85/Sr, and their concentrations in the graphite samples were monitored in situ. The kinetics of cesium sorption and desorption required three to 15 days to establish near-equilibrium concentrations on the graphite. Results of three models, formulated previously by Haire and Zumwalt (1973) to predict mixed-component sorption for sorbates that individually conform to Freundlich behavior, were compared with the observed equilibrium sorption behavior of cesium.

Research Organization:
North Carolina State Univ., Raleigh (USA)
OSTI ID:
5567014
Resource Relation:
Other Information: Thesis (Ph. D.)
Country of Publication:
United States
Language:
English