Cold Crucible Induction Melter (CCIM) Technology is being considered as a possible next generation melter for the Defense Waste Processing Facility (DWPF). Initial and baseline demonstrations that vitrified a Sludge Batch 4 (SB4) simulant at a waste loading of 50 weight percent (versus about 38 weight percent in the current DWPF Melter) were performed by the Nuclear Engineering and Technology Institute (NETEC) in South Korea via a subcontract from the Washington Savannah River Company (WSRC). This higher waste loading was achieved by using a CCIM which can run at higher glass processing temperatures (1250 C and higher) than the current DWPF Melter (1150 C). Higher waste loadings would result in less canisters being filled and faster waste t...
FIDAP has been used to simulate melting of radioactive waste glass in a cold crucible induction heat...
A demonstration of the Cold Crucible Induction Melter (CCIM) technology is currently planned for the...
COGEMA has been vitrifying high-level liquid waste produced during nuclear fuel reprocessing on an i...
Cold crucible induction melters (CCIM) have been proposed as an alternative technology for waste gla...
AREVA Federal Services (AFS) is performing a multi-year, multi-phase Advanced Remediation Technologi...
Over the past few years, Cold Crucible Induction Melter (CCIM) demonstrations have been completed us...
The U.S. Department of Energy (DOE) is currently processing high-level waste (HLW) through a Joule-h...
AREVA Federal Services (AFS) is performing a multi-year, multi-phase Advanced Remediation Technologi...
The cold crucible inductive melting (CCIM) technology successfully applied for vitrification of low-...
In the framework of the Hanford Tank Waste Remediation System (TWRS), the DOE has chosen a multi-ste...
The cold-crucible induction melter (CCIM) design eliminates many materials and operating constraints...
The Idaho National Laboratory (INL) and the St. Petersburg Electrotechnical University “LETI” (ETU) ...
At the present time the primary problem in a closed nuclear fuel cycle is the management of high lev...
The cold-crucible induction melter (CCIM) design eliminates many materials and operating constraints...
About 50 million gallons of high-level mixed waste is currently in storage in underground tanks at T...
FIDAP has been used to simulate melting of radioactive waste glass in a cold crucible induction heat...
A demonstration of the Cold Crucible Induction Melter (CCIM) technology is currently planned for the...
COGEMA has been vitrifying high-level liquid waste produced during nuclear fuel reprocessing on an i...
Cold crucible induction melters (CCIM) have been proposed as an alternative technology for waste gla...
AREVA Federal Services (AFS) is performing a multi-year, multi-phase Advanced Remediation Technologi...
Over the past few years, Cold Crucible Induction Melter (CCIM) demonstrations have been completed us...
The U.S. Department of Energy (DOE) is currently processing high-level waste (HLW) through a Joule-h...
AREVA Federal Services (AFS) is performing a multi-year, multi-phase Advanced Remediation Technologi...
The cold crucible inductive melting (CCIM) technology successfully applied for vitrification of low-...
In the framework of the Hanford Tank Waste Remediation System (TWRS), the DOE has chosen a multi-ste...
The cold-crucible induction melter (CCIM) design eliminates many materials and operating constraints...
The Idaho National Laboratory (INL) and the St. Petersburg Electrotechnical University “LETI” (ETU) ...
At the present time the primary problem in a closed nuclear fuel cycle is the management of high lev...
The cold-crucible induction melter (CCIM) design eliminates many materials and operating constraints...
About 50 million gallons of high-level mixed waste is currently in storage in underground tanks at T...
FIDAP has been used to simulate melting of radioactive waste glass in a cold crucible induction heat...
A demonstration of the Cold Crucible Induction Melter (CCIM) technology is currently planned for the...
COGEMA has been vitrifying high-level liquid waste produced during nuclear fuel reprocessing on an i...