A 233U fuelled reactor for neutron radiography
AbstractAbstract
[en] A compact 233U fuelled neutron source reactor is under construction at the Reactor Research Centre, Kalpakkam, India, to be used primarily for Neutron Radiography of fuel pins, subassemblies and other active components of the Fast Breeder Test Reactor. This BeO reflected source reactor uses approx. 550 gm of 233U as fuel in the form of U-Al alloy plates, and is moderated and natural convection cooled by light water. The reactor is designed to operate at 30 kW nominal power but can be uprated to 100 kW. The neutron flux in the core is as high as approx. 1012 n/cm2s at 30 kW due to the small core size resulting in fluxes of approx. 3 x 106 to 107 n/cm2s at the radiography site. This compact source reactor is located underneath a hot cell where active fuel elements are to be visually examined. A leak tight tube extending down from the cell above permits active objects to be lowered for Neutron Radiography. Sequential pictures will be taken using cassettes driven on a chain conveyor system. Besides the beam for active sample radiography an additional beam would be available for non active sample radiography. The beam tubes are to be provided with standard collimator, aperture control and beam shutter arrangements. (Auth.)
Primary Subject
Secondary Subject
Source
Barton, J.P. (Neutron Radiography Consulting, La Jolla, CA (USA)); Hardt, P. von der (Commission of the European Communities, Petten (Netherlands). Joint Nuclear Research Center) (eds.); 1090 p; ISBN 90-277-1528-9; ; 1983; p. 199-207; D. Reidel; Dordrecht (Netherlands); 1. World conference on neutron radiography; San Diego, CA (USA); 7-10 Dec 1981
Record Type
Book
Literature Type
Conference
Country of publication
Descriptors (DEI)
Descriptors (DEC)
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue