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Jain, G.C., Ganguly, C. (1993) Evaluation of phases in Pu-C-O and (U, Pu)-C-O systems by X-ray diffractometry and chemical analysis. Journal of Nuclear Materials, 207. 169-176 doi:10.1016/0022-3115(93)90259-2

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Reference TypeJournal (article/letter/editorial)
TitleEvaluation of phases in Pu-C-O and (U, Pu)-C-O systems by X-ray diffractometry and chemical analysis
JournalJournal of Nuclear Materials
AuthorsJain, G.C.Author
Ganguly, C.Author
Year1993 (December)Volume207
PublisherElsevier BV
DOIdoi:10.1016/0022-3115(93)90259-2Search in ResearchGate
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Mindat Ref. ID4150785Long-form Identifiermindat:1:5:4150785:6
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Full ReferenceJain, G.C., Ganguly, C. (1993) Evaluation of phases in Pu-C-O and (U, Pu)-C-O systems by X-ray diffractometry and chemical analysis. Journal of Nuclear Materials, 207. 169-176 doi:10.1016/0022-3115(93)90259-2
Plain TextJain, G.C., Ganguly, C. (1993) Evaluation of phases in Pu-C-O and (U, Pu)-C-O systems by X-ray diffractometry and chemical analysis. Journal of Nuclear Materials, 207. 169-176 doi:10.1016/0022-3115(93)90259-2
In(1993) Journal of Nuclear Materials Vol. 207. Elsevier BV

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Jain, G.C., Ganguly, C. (1993) Experimental evaluation of oxygen solubility in UN, PuN and (U, Pu) N. Journal of Nuclear Materials, 202 (3). 245-251 doi:10.1016/0022-3115(93)90394-e
Pillon, S., Ingold, F., Fischer, P., Andre, G., Botta, F., Stratton, R.W. (1993) Investigation of the UONa and (U,Pu)ONa phase diagrams — Study of Na3UO4 and Na3(U,Pu)O4 phases. Journal of Nuclear Materials, 206 (1). 50-56 doi:10.1016/0022-3115(93)90231-m
Ganguly, C., Hegde, P.V., Jain, G.C., Basak, U. (1991) Fabrication of (U, Pu)C and (U, Pu)N Fuels for FBTR and PFBR. Materials Science Forum, 48. 153-174 doi:10.4028/www.scientific.net/msf.48-49.153
Ganguly, C., Hegde, P.V., Sengupta, A.K. (1991) Preparation, characterisation and out-of-pile property evaluation of (U,Pu)N fuel pellets. Journal of Nuclear Materials, 178 (2). 234-241 doi:10.1016/0022-3115(91)90391-j
Kutty, T.R.G., Ganguly, C. (1993) Identation creep of Zircaloy-2 welds of nuclear fuel pins. Journal of Nuclear Materials, 207. 345-349 doi:10.1016/0022-3115(93)90279-8
Benedict, U., Dufour, C., Scholten, O. (1978) Lattice parameter variation of PuC, PuN, and Pu(C, N) between 50 and 300 K. Journal of Nuclear Materials, 73 (2). 208-212 doi:10.1016/0022-3115(78)90562-7
Matzke, Hj., Lambert, R.A. (1974) The evaporation behavior and metal self-diffusion processes in (U,Pu)C and (U,Pu)O2. Journal of Nuclear Materials, 49 (3). 325-328 doi:10.1016/0022-3115(74)90045-2
Diels, P., Lecocq, R. (1982) Determination of the Pu/U+Pu ratio in FBR fuel pellets by X-ray fluorescence analysis. Journal of Nuclear Materials, 106 (1). 115-120 doi:10.1016/0022-3115(82)90340-3
Rosen, S., Nevitt, M.V., Mitchell, A.W. (1963) Metallographic and X-ray observations of Pu-C alloys. Journal of Nuclear Materials, 10 (2). 90-98 doi:10.1016/0022-3115(63)90074-6
Rest, J. (1993) Kinetics of fission-gas-bubble-nucleated void swelling of the alpha-uranium phase of irradiated U-Zr and U-Pu-Zr fuel. Journal of Nuclear Materials, 207. 192-204 doi:10.1016/0022-3115(93)90261-v
Bradbury, M.H., Matzke, Hj. (1980) Self-diffusion of plutonium in high burn-up simulated (U, Pu) (C, N) and (U, Pu) N. Journal of Nuclear Materials, 91 (1). 13-22 doi:10.1016/0022-3115(80)90027-6
 
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