Refine your search:     
Report No.
 - 
Search Results: Records 1-3 displayed on this page of 3
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Oral presentation

Effects of steel overpack on aqueous alteration of vitrified high-level radioactive waste

Iwata, Hajime; Mitsui, Seiichiro; Sekine, Nobuyuki*

no journal, , 

In order to measure Fe-silicates precipitated under geological disposal conditions, a static leaching test has been conducted of simulated vitrified waste in 0.01 M FeCl$$_{2}$$ solution with a surface area to volume ratio = 10 m$$^{-1}$$ at 90$$^{circ}$$C under a N$$_{2(g)}$$ atmosphere. Obtained results indicate that Fe bearing minerals change from green rust to Fe-rich serpentine over time. Such mineral transitions are important as they may have an effect on the alteration behavior of glasses used for geological disposal of HLW.

Oral presentation

Development of stress-strain analysis with synchrotron radiation X-ray for simulated waste glass samples

Tominaga, Aki; Shobu, Takahisa; Sato, Seiichi*; Hatakeyama, Kiyoshi*; Nagai, Takayuki

no journal, , 

High level radioactive vitrified materials are subject to monitoring during decades at storage facilities and over tens of thousands of years at final disposal sites. Although sufficient structural stability for long-term storage is necessary, high effluent filling which is often incompatible with mechanical and chemical integrity are required. The inhomogeneity of the glass yielded in preparation will cause the instability of the glass. Residual stress is one of the important parameters for evaluating the stability of the vitrified materials. Conventional stress measurement using a strain gauge reveal the averaged stress of whole specimen, however, local stress is also important because it can be an origin of the deformation or crack. Therefore, we developed a method using high-energy synchrotron X-ray stress measurements to clarify the local strain of the vitrified materials. Moreover, stress of each structural component such as crystalline and glass matrix can be separated by the method.

Oral presentation

Pair distribution function analysis of simulated nuclear waste glass

Yoneda, Yasuhiro; Tsuji, Takuya; Matsumura, Daiju; Okamoto, Yoshihiro; Nagai, Takayuki

no journal, , 

In order to establish vitrification technology, it is important to clarify how various substances dispersed in glass exist. We made simulated glass by mixing various substances containing metallic element of the platinum group with raw material glass containing SiO$$_2$$-B$$_2$$O$$_3$$ glass as the main component. This simulated glass was heated to 600$$^{circ}$$C just above the melting point and observed by an X-ray diffraction experiment. The obtained X-ray diffraction profile revealed the local structure using the pair distribution function (PDF). Since the network structure of SiO$$_2$$ is strong, it is considered that the precipitated fine particles become wedges and the Si-O bond length is modulated.

3 (Records 1-3 displayed on this page)
  • 1