Radioactive tracer test to develop a recycling system for operating reactor scrap metal
Conference
·
OSTI ID:382917
- Mitsubishi Materials Corp., Tokyo (Japan). Nuclear Energy Center
- Radioactive Waste Management Center, Tokyo (Japan)
A demonstration test using radio-isotope (RI) tracers during the manufacturing of inner drum shielding material from the recycling of operating reactor scrap metal was completed and the following results were obtained. The behavior of five radionuclides (Mn-54, Co-60, Zn-65, Sr-85 and Cs-137) was established. The time-dependent behaviors of the radionuclides in molten steel and in slag were investigated. The radioactivity distributions in metal products were homogeneous. Dose equivalent rates in the working area were below background levels and radioactive dust concentrations in the air were below detection limits.
- OSTI ID:
- 382917
- Report Number(s):
- CONF-941075-; ISBN 1-55899-253-7; TRN: 96:025809
- Resource Relation:
- Conference: 18. international symposium on the scientific basis for nuclear waste management, Kyoto (Japan), 23-27 Oct 1994; Other Information: PBD: 1995; Related Information: Is Part Of Scientific basis for nuclear waste management 18. Part 2; Murakami, Takashi [ed.] [Ehime Univ., Matsuyama, Ehime (Japan). Dept. of Earth Sciences]; Ewing, R.C. [ed.] [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Earth and Planetary Sciences]; PB: 690 p.; Materials Research Society symposium proceedings, Volume 353
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
05 NUCLEAR FUELS
SCRAP METALS
WASTE PRODUCT UTILIZATION
SHIELDING MATERIALS
CONTAINERS
NUCLEAR POWER PLANTS
RADIOACTIVE WASTE PROCESSING
MANGANESE 54
COBALT 60
ZINC 65
STRONTIUM 85
CESIUM 137
DISTRIBUTION
RADIOACTIVE WASTE FACILITIES
DESIGN
DOSE RATES
INDUCTION FURNACES
CASTINGS
MACHINING
OFF-GAS SYSTEMS
SCRAP METALS
WASTE PRODUCT UTILIZATION
SHIELDING MATERIALS
CONTAINERS
NUCLEAR POWER PLANTS
RADIOACTIVE WASTE PROCESSING
MANGANESE 54
COBALT 60
ZINC 65
STRONTIUM 85
CESIUM 137
DISTRIBUTION
RADIOACTIVE WASTE FACILITIES
DESIGN
DOSE RATES
INDUCTION FURNACES
CASTINGS
MACHINING
OFF-GAS SYSTEMS