-
Article
Design, installation and preliminary flux measurements at the Fast Flux Experimental Facility (FFEF) of the Fast Breeder Test Reactor (FBTR)
Design and installation of an experimental cavity just above the central subassembly in Fast Breeder Test Reactor has been accomplished. This paper describes the modification details of the central canal plug ...
-
Article
Luminescent versus non-luminescent uranyl–picolinate complexes
Luminescence of uranyl ion (UO22+) complexed with picolinate (PA) has been studied in aqueous and acetonitrile medium. In aqueous medium, for UO22+ to PA ratio of up to 1:20, a 1:1 non-luminescent specie with sta...
-
Article
Thermodynamic data of U3Ga5 from calorimetric measurements
U3Ga5, an intermetallic compound in the U–Ga system was prepared by arc melting method and characterised using X-ray diffraction technique. Enthalpy increment measurements on this compound were carried out in the...
-
Article
Direct burn-up determination of fast reactor mixed oxide (MOX) fuel by preferential evaporation of interfering elements
Spent fuel of uranium–plutonium mixed oxide (MOX) from sodium cooled Fast Breeder Test Reactor (FBTR) was analyzed for at.% burn-up by preferential evaporation method. A sequential pattern of analysis of fissi...
-
Article
Dissolution and characterisation studies on U–Zr and U–Pu–Zr alloys in nitric acid medium
Dissolution of metallic alloys, U–Zr and U–Pu–Zr has been investigated in HNO3 media. An electro oxidative dissolution technique was also examined. Explosive nature of metallic alloys during dissolution in nitric...
-
Article
Preferential removal of Sm by evaporation from Nd–Sm mixture and its application in direct burn-up determination of spent nuclear fuel
Rate of evaporation of Sm and Nd from their mixture was studied based on their ion intensities using thermal ionization mass spectrometry. Because of the comparatively larger evaporation rate of Sm, it was fou...