Experience of Glass Melter Operation in Tokai Vitrification Facility

2001 ◽  
Author(s):  
Jiro Nakayama ◽  
Masahiro Yoshioka
Keyword(s):  
Water Injection ◽  
Liquid Waste ◽  
The Other ◽  
Injection System ◽  
Exhaust Pipe ◽  
High Level Liquid Waste ◽  
Glass Melter ◽  
High Level ◽  
Air Film ◽  
Reprocessing Plant

Abstract Tokai Vitrification Facility (TVF) is the first plant in Japan to immobilize the High-Level Liquid Waste (HLLW) transferred from Tokai Reprocessing Plant (TRP) to the borosilicate glass. Two problems happened through the plant operation, and the investigations to solve them are being carried on. One is the deposit that is caused by the cohesion of the dust inside the air-film cooler (a type of the exhaust pipe) of the glass melter and the other is the accumulation of noble metal elements in the HLLW on the melter bottom. The countermeasure for the former is the water injection system and for the latter is the reform of the melter bottom structure.

The Behavior of Radiolytically Produced Hydrogen in a High-Level Liquid Waste Tank of a Reprocessing Plant: Hydrogen Concentration in the Ventilated Tank Air

2015 ◽  
Vol 189 (2) ◽  
pp. 122-132 ◽  
Author(s):  
Hiroshi Kinuhata ◽  
Yoji Shirato ◽  
Masahiro Tomiyama ◽  
Takashi Kodama ◽  
Masanao Nakano ◽  
...  
Keyword(s):  
Hydrogen Concentration ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level ◽  
Reprocessing Plant

Boiling and drying accident of high-level liquid waste in a reprocessing plant: Examination of the NO2 and NO generation using the simulated waste

2020 ◽  
Vol 57 (9) ◽  
pp. 1101-1110
Author(s):  
Takashi Kodama ◽  
Hiroshi Kinuhata ◽  
Yuki Shibata ◽  
Mikio Kumagai ◽  
Kazunori Suzuki ◽  
...  
Keyword(s):  
Liquid Waste ◽  
High Level Liquid Waste ◽  
Simulated Waste ◽  
High Level ◽  
Reprocessing Plant

Study on the Behavior of Radiolytically Produced Hydrogen in a High-Level Liquid Waste Tank of a Reprocessing Plant: Comparison between Actual and Simulated Solutions

2015 ◽  
Vol 192 (2) ◽  
pp. 155-159
Author(s):  
Hiroshi Kinuhata ◽  
Masahiko Yamamoto ◽  
Shigeo Taguchi ◽  
Naoki Surugaya ◽  
Soichi Sato ◽  
...  
Keyword(s):  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level ◽  
Reprocessing Plant

Release of Radioactive Materials from Simulated High-Level Liquid Waste at Boiling Accident in Reprocessing Plant

2015 ◽  
Vol 190 (2) ◽  
pp. 207-213 ◽  
Author(s):  
S. Tashiro ◽  
G. Uchiyama ◽  
Y. Amano ◽  
H. Abe ◽  
Y. Yamane ◽  
...  
Keyword(s):  
Liquid Waste ◽  
High Level Liquid Waste ◽  
Radioactive Materials ◽  
High Level ◽  
Reprocessing Plant

Modeling on Evaporation Characteristics of a Reprocessing Plant High-Level Liquid Waste Concentrator

1990 ◽  
Vol 92 (2) ◽  
pp. 238-242 ◽  
Author(s):  
Masanori Takahashi ◽  
Tatsuo Izumida ◽  
Fumio Kawamura ◽  
Hideo Yusa
Keyword(s):  
Liquid Waste ◽  
High Level Liquid Waste ◽  
High Level ◽  
Reprocessing Plant

Challenges During the Decommissioning of the WAK Site: Dismantling of Highly Contaminated HLLW-Storage Tanks

2009 ◽  
Author(s):  
Joachim Dux ◽  
Oliver Fath
Keyword(s):  
Concrete Structures ◽  
Liquid Waste ◽  
Nuclear Test ◽  
Process Equipment ◽  
Storage Tanks ◽  
Nuclear Fuels ◽  
High Level Liquid Waste ◽  
Test Operation ◽  
High Level ◽  
Reprocessing Plant

The German pilot reprocessing plant WAK was shut down in 1990 after reprocessing about 200 Mg of nuclear fuels and is decided to be dismantled completely to the green field until year 2023. During the years 1994 until 2008 approximately 2.000 Mg of partly highly contaminated process equipment and 1.500 Mg of concrete structures corresponding to 99% of the radioactive inventory of 5E14 Bq of the WAK reprocessing building have already been dismantled. A major prerequisite for the complete dismantling of the WAK is the management of the 60 m3 high-level liquid waste (HLLW) with a total β/γ-activity of 8.0E17 Bq resulting from reprocessing. For this purpose the Karlsruhe Vitrification Plant (VEK) was constructed in the years between 2000 and 2005 and inactively tested in 2007. The subsequent nuclear test operation and routine hot operation of the VEK plant are planned to start mid-2009. In parallel to vitrification operation, dismantling of the four HLLW tanks in the storage buildings will be prepared for remote dismantling.

Decommissioning of Buildings 105X and 122X at Belgoprocess

2009 ◽  
Author(s):  
Bart Ooms ◽  
Bert Lievens ◽  
Wim Van Laer ◽  
Etienne Van Campfort ◽  
Robert Walthe´ry
Keyword(s):  
Research Reactor ◽  
Liquid Waste ◽  
High Level Liquid Waste ◽  
Appropriate Treatment ◽  
Time Gap ◽  
Enriched Uranium ◽  
High Level ◽  
And Storage ◽  
Reprocessing Plant ◽  
Aircraft Crash

The Eurochemic reprocessing plant was built between 1960 and 1966 and operated from 1966 until the end of 1974. During these eight years of active operation, Eurochemic reprocessed 181.5 t of natural and slightly enriched uranium fuels (less than 4.5% initial 235U enrichment) from various experimental and power reactors, and 30.6 t high enriched uranium fuels from testing reactors, generating approximately 50 m3 of high-level liquid waste from power reactor fuels (LEWC, low enriched waste concentrate ) and 850 m3 from research reactor fuels (HEWC, high enriched waste concentrate). As a result of reprocessing and cleaning operations (1975–1981), generated intermediate and high level wastes were put into temporary storage, pending the availability of appropriate treatment, conditioning and storage facilities. Immediately after LEWC and HEWC vitrification, the corresponding storage vessels were rinsed and decontaminated. The rinsing and decontamination program started in April 1986 and was interrupted between September 1987 and July 1989 in view of possibly reusing the vessels for storage of similar HLLW (high level liquid waste) solutions. Because the storage building itself was not aircraft crash resistant, it was decided not to use the storage vessels anymore and to proceed the decontamination with more aggressive chemicals. Due to this time gap however, and especially because vitrification came to an end in September 1991, a considerable volume of decontamination liquids was produced after this time and stored, pending the availability of the bituminization installation. In 2005 and 2006 a research program was performed. For both buildings and vessels images and samples were collected and dose rate measurements were executed. The paper presents an overview of the different studies that were indispensable in order to be able to select the most appropriate decommissioning strategy.

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