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Growth behavior of surface layers on simulated waste glass during two different types of leaching has been studied associated with their corrosion kinetics. Static and Soxhlet leach tests were performed in distilled water at a temperature of 100 degrees celsius. Auger and ESCA analyses of solid samples after leaching showed that the layers consisted of two or three sublayers which were distinguished by their different components. The transition elements Fe and Ni, the rare - earths Nd and La,and Zn were concentrated in the layers, while Si, B and alkali were depleted in most of the layers. Growth kinetics of the layers followed approximately linear relations for the two types of leaching. Growth rates and elemental profiles of the layers depended upon the leaching conditions. Comparison between the leaching rate and the thickness of the layer showed that layers did not work as effective diffusion barriers untill the threshold thickness, which depended on the layer structures.

JAEA Reports

Development of High-Level Liquid Waste Solidification in PNC

; ; Nagaki, Hiroshi

PNC TN841 82-26, 12 Pages, 1982/04

PNC-TN841-82-26.pdf:0.5MB

R&D activities on the solidificationof HLLW and related technologies arebeing performed with the aim of designingand constructing the HLLWSolidification Pilot Plant at Tokai whichis planned to start operations in 1987. Solidified waste forms and compositionshave been studied with the aid of characte-rizing solidified products and evaluatingsolidification technologies, and twotypical series of borosilicate glass produ-cts have been found to be feasible for thesolidification of HLLW generated by theTokai Reprocessing Plant. The HLLW Engineering Test Facility (FTF) with denitration and concentrationequipment, two different types of Joule-heated ceramic melters, offgas treatmentequipment and a canister handling system,has been in opcration since February 1980in order to obtain various kinds of engin-eering data and perspectives. Air-coolinglests are also in progress to charaterizenatural or forced convection heat transferin the storage of the HLLW solidifiedwaste.

JAEA Reports

None

Tsunoda, Naomi; Sasaki, Noriaki; Nagaki, Hiroshi

PNC TN841 80-22, 104 Pages, 1980/04

PNC-TN841-80-22.pdf:6.4MB

no abstracts in English

JAEA Reports

Development of vitrification technique of HLLW in engineering scale at PNC

Nagaki, Hiroshi; Ogino, Naohiko*; Tsunoda, Naomi; Segawa, Takeshi*

PNC TN841 79-54, 18 Pages, 1979/10

PNC-TN841-79-54.pdf:0.35MB

Some processes have been investigated to develop the technology of solidification of the high level radio active liquid waste generated from the nuclear fuel reprocessing plant at PNC. This report covers the present state of development of a joule heated ceramic melter and a direct megahertz induction heated furnace. An engineeing scale test has been performed by both of these melters. A joule heated melter could treat 45 kg glass an hour or 16 1/hr. A direct induction furnace was able to melt 5 kg glass per an hour or 1.8 1/hr. Both of the meltes were composed of refractory ceramics and electro-fused cast. Therefore, glass could be melted at above 1200 degrees celsius. At the higher temperature melting, the glass would be the more reliable, in general.

JAEA Reports