Journal of Nuclear Engineering & Technology
Volume 5, Issue 3 (2015)
Published
Table of contents
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Analysis of Pressurized Water Reactor Fuel Rod Using Nano Fluid
Abstract: The project aims at analysing the flow through a PWR Nuclear Fuel Rod. In this analysis, fuel rod is simulated using ANSYSCFX 14. Fuel Rod is simulated along with the Spacer Grid. The project aims at studying the behaviour of nano fluids under laminar flow conditions and its application as Nuclear reactor coolants. The properties of two nano fluids have been studied-Al2O3 and CuO with water as base fluid. Their …
Published in Journal of Nuclear Engineering & Technology · Vol. 5, Issue 3, 2015 Read article
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Study the Effect of Gd2O3 on the Neutronic Characteristics of Boiling Water Reactor using MCNPX Code
Abstract: MCNPX code (Monte Carlo N–Particle code extended) is used to design Boiling Water Reactor (BWR) bundle model. This model is designed to study the effect of Gd2O3 on the reactivity effect of voiding, void coefficient, neutron flux and normalized power. The incorporation of Gd2O3 directly into the UO2 fuel is the most attractive process, because of its significant effect on the fuel life in the core of the reactor. The …
Published in Journal of Nuclear Engineering & Technology · Vol. 5, Issue 3, 2015 Read article
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Estimation of PVT Properties and Vapor Pressure of CHON Based Extractants for Nuclear Solvent Extraction
Abstract: CHON amides like N, N′-Di hexyl octanamide (DHOA) and N, N′-Di octyl hexanamide (DOHA) have been identified as the alternate extractants to TBP for nuclear solvent extraction. Critical properties of these amidic solvents are needed for the estimation of various physical properties. Currently, there is little information in the literature about critical properties for these solvents. For these two extractants, critical properties and boiling point were estimated using group contribution …
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Volumetric Properties of PEG-400 in FS-13 Diluent for 293.15 K to 343.15 K at 0.1 MPa
Abstract: PEG-400 in FS-13 solvent was proposed for strontium extraction from spent fuel solution in back end of nuclear fuel cycles. Densities and viscosities of solutions of PEG-400 and FS-13 were not available in literature. Densities and viscosities of binary mixture of extractant PEG-400 in FS-13 diluent was measured from 293.15 to 323.15 K. The excess molar volume (VE) and excess Gibb’s free energy of activation (DGE) was evaluated from density …
Published in Journal of Nuclear Engineering & Technology · Vol. 5, Issue 3, 2015 · pp. 1–5 Read article
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Radio-Assay of Plant Samples at the Proposed Nuclear Reactor Site in Geregu, North-Central Nigeria
Abstract: Radio-assay of plant samples at the Geregu site, North-Central Nigeria, was evaluated to determine the radiological burden on the environment. Plant samples were collected from ten different locations on the site and the concentrations were measured using gamma spectroscopy. Radiological equivalent dose was estimated using standard analytical methods. The mean value for the external outdoor absorbed gamma dose rates due to terrestrial γ-rays from the nuclides Ra-226, Th-232 and K-40 …
Published in Journal of Nuclear Engineering & Technology · Vol. 5, Issue 3, 2015 · pp. 6–13 Read article