Refine your search:     
Report No.
 - 
Search Results: Records 1-2 displayed on this page of 2
  • 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

Journal Articles

Phase analysis of simulated nuclear fuel debris synthesized using UO$$_{2}$$, Zr, and stainless steel and leaching behavior of the fission products and matrix elements

Tonna, Ryutaro*; Sasaki, Takayuki*; Kodama, Yuji*; Kobayashi, Taishi*; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; Kumagai, Yuta; Kusaka, Ryoji; Watanabe, Masayuki

Nuclear Engineering and Technology, 55(4), p.1300 - 1309, 2023/04

 Times Cited Count:2 Percentile:84.55(Nuclear Science & Technology)

Simulated debris was synthesized using UO$$_{2}$$, Zr, and stainless steel and a heat treatment method under inert or oxidizing conditions. The primary U solid phase of the debris synthesized at 1473 K under inert conditions was UO$$_{2}$$, whereas a (U,Zr)O$$_{2}$$ solid solution formed at 1873 K. Under oxidizing conditions, a mixture of U$$_{3}$$O$$_{8}$$ and (Fe,Cr)UO$$_{4}$$ phases formed at 1473 K whereas a (U,Zr)O$$_{2+x}$$ solid solution formed at 1873 K. The leaching behavior of the fission products from the simulated debris was evaluated using two methods: the irradiation method, for which fission products were produced via neutron irradiation, and the doping method, for which trace amounts of non-radioactive elements were doped into the debris. The dissolution behavior of U depended on the properties of the debris and aqueous medium the debris was immersed in. Cs, Sr, and Ba leached out regardless of the primary solid phases. The leaching of high-valence Eu and Ru ions was suppressed, possibly owing to their solid-solution reaction with or incorporation into the uranium compounds of the simulated debris.

Oral presentation

Composition optimization of iron phosphate glasses for radioactive sludge

Takebe, Hiromichi*; Kitamura, Naoto*; Amamoto, Ippei; Kobayashi, Hidekazu; Mitamura, Naoki*; Tsuzuki, Tatsuya*

no journal, , 

The great amount of water used for cooling the stricken power reactors at Fukushima Dai-ichi following the earthquake and tsunami on March 11, 2011 has resulted in the accumulation of the remaining water. The water is subsequently contaminated by fission products and some other radioactive substances. The initial treatment to remove the radioactive substances from the cooling water again produced a secondary radioactive waste, the sludge. Iron phosphate glass powder/frit and main component of raw materials for simulated sludge, e.g., barium sulfate and potassium nickel ferrocyanide with various concentrations, were mixed for melting batch. The temperature required for the formation of homogeneous melt was determined by the direct observation of sample decomposition and melting processes on the thermocouple filament through a microscope. The mixtures for bulk glasses were melted in air using platinum crucibles. The quenched glass samples consisted mainly of oxide constituents due to the decomposition of the sludge components during heating and melting processes. Characteristic temperatures of glass transition, Tg, and onset of crystallization, Tx, was determined by differential thermal analysis. Thermal stability against crystallization for the glass samples was evaluated by the temperature difference between Tx and Tg. Water durability was determined by the weight change per a specific surface area after immersion test in hot water at 120$$^{circ}$$C for 72 hours based on MCC-2 static leaching method. Phosphate network species and chemical bonding were characterized by Raman spectroscopy. Glass composition melted with the stimulated sludge components is optimized in terms of both thermal stability and water durability with the characterization of O/P molar ratio.

2 (Records 1-2 displayed on this page)
  • 1