Laser and plasma technology division annual report 1992.

By:

Venkatramani, N

Contributor(s):

Material type: Text

TextLanguage: en Publication details: Bombay : BARC, 1993.Description: 131 p

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Item type	Home library	Call number	Status	Barcode
Books	Centro de Información Eduardo Savino	BARC-1993-P-004 (Browse shelf(Opens below))	Available	41020

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61 The solid solubility of Ni and Co in ÓZr: A secondary ion mass spectrometry study.
by Zou, H.
62 Dissolution models for glassy waste forms.
by Harvey, K. B.
63 A particletracking code [TRACK3D] for convective solute transport modelling in the geosphere:description and user's manual.
by Nakka, B.W.
64 Application of the integral method to modelling the oxidation of defected fuel elements.
by Kolár, Miroslav
65 Radiological assessment of 36Cl in the disposal of used CANDU fuel.
by Johnson, L.H.
66 Estimating the lifetimes of titanium containers for nuclear fuel waste: a damage function for the crevice corrosion of grade2 titanium.
by Shoesmith, David W.
67 Deposition of corrosion products incore.
by Burril, K.A.
68 Numerical simulations of groundwater flow and solute transport in the lake 233 aquifer.
by Klukas, M. H.
69 Laser plasma generation of hydrogenfree diamondlike carbon thin films on Zr2.5Nb CANDU pressure tube materials and silicon wafers with a pulsed highpower CO2 laser.
by Ebrahim, N. A.
70 Upgrading elastomer seals for nuclear service.
by Wittich, K. C.
71 An approach to underground characterization of a disposal vault granite.
by Everitt, R. A.
72 An assessment of the feasibility of indifinite containment of Canadian Nuclear fuel wastes.
by Shoesmith, David W.
73 14C Measurement: Effect of variations in sample preparation and storage on the counting efficiency for 14C using a carbo-sorb/permafluor E+ liquid scintillation coktail.
by Kramer, S. J.
74 The Anisotropy of Hf Diffusion in Ó-Zr.
by Hood, G. M.
75 Role of internal stresses in the transient of irradiation growth of Zircaloy-2.
by Tomé, C. N.
76 Managhement of the installation of a 10 MeV, 50 kW Electron-beam irradiator.
by Lawrence, C. B.
77 Assessment of the longterm risks of inadvertent human intrusion into a proposed Canadian nuclear fuel waste disposal vault in deep plutonic rock: Revision 1.
by Wuschke, D. M.
78 The volumes of wastes resulting from the direct disposal or recycling of CANDU used fuel.
by Harvey, K. B.
79 Crevice corrosion behaviour of titanium grades2 and 12 in hot aqueous chloride solution: the effect of chloride concentration.
by Bailey, M. Grant
80 Regional groundwater flow in the Atikokan Research Area: model development and calibration.
by Ophori, Duke U.
81 Comparison of the mineralogical composition, physical, swelling and hydraulic properties of untreated sodium bentonites from Canada, the United States and Japan.
by Dixon, D. A.
82 Regional groundwater flow in the Atikokan Research Area: spatially variable density and viscosity.
by Ophori, Duke U.
83 Estimation of uncertainties in predictions of environmental transfer models: evaluation of methods and applications to CHERPAC.
by Koch, J.
84 Coolability of severely degraded CANDU cores.
by Meneley, D. A.
85 Neutronphoton energy deposition in CANDU reactor fuel channels: a comparison of modelling techniques using ANIS and MCNP computer codes.
by Bilanovic, Z.
86 The Cigar Lake uranium deposit: analog information for Canada's nuclear fuel waste disposal concept.
by Cramer, J. J.
87 Crosslinking of commercial polyethylenes by 10 MeV electrons.
by Singh, Ajit
88 Crystal structure of thin oxide films grown on ZrNb alloys studied by RHEED [Reflection High Energy Electron Diffraction].
by Khatamian, D.
89 A revised conceptual hydrogeologic model of a crystalline rock environment, Whiteshell Research Area, Southeastern Manitiba, Canada.
by Stevenson, D. R.
90 Fissionproduct tellurium and cesium telluride chemistry revisited.
by McFarlane, J.