Spent fuel transport and reprocessing

Conference · Tue Jan 01 04:00:00 EST 1985 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5065283

Prasad, A N; Rao, M K; Seetharamiah, P

The reprocessing experience in India started with the commissioning in 1964 at Trombay a plant designed to handle metallic uranium fuels from research reactors. This was entirely executed by indigenous effort. Since then the reprocessing programme has evolved in stages matching with the growth of nuclear programme. The reprocessing plant at Tarapur, under operation at present, is the next one to be built capable of reprocessing uranium oxide fuels from the power reactors at Rajasthan (PHWR) and Tarapur (BWR). The third plant now under construction will reprocess the spent fuels from the power reactors (PHWR) and the Fast Breeder Test Reactor (FBTR) located at Kalpakkam. By this planned progressive approach considerable experience has been acquired which will be useful in the design and construction of even larger plants to meet the projected demands. Setting up of a larger plant is being planned. To meet the increasing demands for movement of spent fuel arisings from reactors to reprocessing plants, transportation casks, each weighing up to 70 tonnes, have been designed and manufactured within the country. These casks each conform to test standards stipulated in the IAEA transport regulations. This paper discusses the experience in aspects dealing with spent fuel transport and reprocessing.

• Research Organization: Bhabha Atomic Research Centre, Bombay, India
• OSTI ID: 5065283
• Report Number(s): CONF-850514-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 49, Suppl. 1
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
210500 -- Power Reactors
Breeding
ACTINIDES
ALLOYS
ASIA
BREEDER REACTORS
BWR TYPE REACTORS
CANDU TYPE REACTORS
CASKS
CLEANING
CONSTRUCTION
CONTAINERS
DECONTAMINATION
DESIGN
DEVELOPING COUNTRIES
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL REPROCESSING PLANTS
FUELS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
INDIA
KALPAKKAM LMFBR REACTOR
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
METALS
NATURAL URANIUM REACTORS
NUCLEAR FACILITIES
NUCLEAR FUELS
PHWR TYPE REACTORS
PLANNING
POWER REACTORS
PRESSURE TUBE REACTORS
RAJASTHAN-1 REACTOR
RAJASTHAN-2 REACTOR
REACTOR MATERIALS
REACTORS
REPROCESSING
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SEPARATION PROCESSES
SPENT FUEL CASKS
SPENT FUELS
TARAPUR-1 REACTOR
TARAPUR-2 REACTOR
TEST REACTORS
THERMAL REACTORS
THORIUM
TIN ALLOYS
TRAINING
TRANSPORT
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS