Design, Development and Operational Experience of Demonstration Facility for Cs-137 Source Pencil Production at Trombay - 13283
- Technology Development Division, Nuclear Recycle Group, Bhabha Atomic Research Centre, Mumbai (India)
Radioactive waste management is a vital aspect of any nuclear program. The commercial feasibility of the nuclear program largely depends on the efficiency of the waste management techniques. One of such techniques is the separation of high yield radio-nuclides from the waste and making it suitable for medical and industrial applications. This will give societal benefit in addition to revenue generation. Co-60, the isotope presently being used for medical applications, needs frequent replacement because of its short half life. Cs-137, the major constituent of the nuclear waste, is a suitable substitute for Co-60 as a radioactive source because of its longer half life (28 years). Indian nuclear waste management program has given special emphasis on utilization of Cs-137 for such applications. In view of this a demonstration facility has been designed for vitrification of Cs-137 in borosilicate glass, cast in stainless steel pencils, to be used as source pencils of 300 Ci strength for blood irradiation. An induction heated metallic melter of suitable capacity has been custom designed for the application and employed for the Cs-137 pencil fabrication facility. This article describes various systems, design features, experiments and resulting modifications, observations and remote handling features necessary for the actual operation of such facility. The layout of the facility has been planned in such a way that the same can be adopted in a hot cell for commercial production of source pencils. (authors)
- Research Organization:
- WM Symposia, 1628 E. Southern Avenue, Suite 9-332, Tempe, AZ 85282 (United States)
- OSTI ID:
- 22225020
- Report Number(s):
- INIS-US-13-WM-13283; TRN: US14V0473045975
- Resource Relation:
- Conference: WM2013: Waste Management Conference: International collaboration and continuous improvement, Phoenix, AZ (United States), 24-28 Feb 2013; Other Information: Country of input: France; 4 refs.
- Country of Publication:
- United States
- Language:
- English
Similar Records
Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle
Crickets{sup TM} and Curies: Lessons Learned from the Steel Industry - 18221
Related Subjects
07 ISOTOPES AND RADIATION SOURCES
BOROSILICATE GLASS
CAPACITY
CESIUM 137
COBALT 60
DESIGN
EFFICIENCY
HOT CELLS
INDIA
IRRADIATION
RADIATION SOURCES
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTES
REMOTE HANDLING
STAINLESS STEELS