Experience with fuel handling system of FBTR
- 1. ROMG, FBTR, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
Description
Fast Breeder Test Reactor (FBTR) is a 40 MWt.13.2 MWe sodium cooled mixed carbide fuelled reactor. Fuel handling in FBTR is a group of operations, consisting of charging of fresh fuel, and discharging of irradiated fuel from the reactor. These operations were done with the help of charging and discharging flasks. There is a provision for in-pile transfer of subassemblies using transfer flask. Transfer of subassemblies is done for storage of irradiated fuel subassemblies in periphery for cooling, prior to discharging. During fuel handling, to provide guiding the gripper tube a guide tube of about 6 m long is introduced in to the fuel-handling canal. To approach any position in the grid plate, a system of two rotatable plugs, located eccentric to each other and a fuel-handling canal located in smaller plug is used. Fuel handling is carried out with the reactor in shut down state. In May 1987 during fuel subassembly transfer operation from core to periphery, an incident of jamming of the fuel sub-assembly in fuel handling guide tube was encountered. This paper summarizes the activities carried out to normalize the fuel handling system after the fuel handling incident, modifications carried out and experience with the fuel handling system since then. (author)
Additional details
Publishing Information
- Publisher
- Prime Time Education
- Imprint Place
- Mumbai (India)
- ISBN
- 81-8372-028-5
- Imprint Title
- Proceedings of national conference on operating experience of nuclear reactors and power plants: book of preprints
- Imprint Pagination
- 1313 p.
- Journal Page Range
- p. 477-485
Conference
- Title
- operating experience of nuclear reactors and power plants; NRT-3: 3. nuclear reactor technology
- Acronym
- OPENUPP-2006
- Dates
- 13-15 Nov 2006
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 38040228
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; FUEL ASSEMBLIES; INSPECTION; KALPAKKAM LMFBR REACTOR; MIXED CARBIDE FUELS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY
- Descriptors DEC
- BREEDER REACTORS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; NUCLEAR FUELS; OPERATION; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS; SAFETY; SOLID FUELS; TEST FACILITIES; TEST REACTORS
Optional Information
- Notes
- 13 figs., 1 tab.