Nuclear Engineering and Design 241 (2011) iii–v
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Nuclear Engineering and Design j o u r n a l h o m e p a g e : w w w . e l s e v i e r. c o m / l o c a t e / n u c e n g d e s
CONTENTS (W3MDM) University of Leeds International Symposium: What Where When – Multi-dimensional Advances for Industrial Process Monitoring Guest Editors: Robert Hammond and Mi Wang W3MDM Special Section Multi-dimensional advances for industrial process monitoring R. Hammond and M. Wang Characterization of crystallisation processes with electrical impedance spectroscopy Y. Zhao, M. Wang and R.B. Hammond The “thousand words” problem: Summarizing multi-dimensional data D.M. Scott Image reconstruction in electrostatic tomography using a priori knowledge from ECT B. Zhou, J. Zhang, C. Xu and S. Wang Determination of the distribution of air and water in porous media by electrical impedance tomography and magnetoelectrical imaging F.-H. Haegel, E. Zimmermann, O. Esser, K. Breede, J.A. Huisman, W. Glaas, J. Berwix and H. Vereecken Generalized flow pattern image reconstruction algorithm for electrical capacitance tomography S. Liu, J. Lei, Z.H. Li, Z.X. Han, J.T. Li and Q. Chen Ultrasound Vibration Potential measurement techniques for imaging H.I. Schlaberg, M. Wang, P. Guan and J.I. Khan Spatial resolution analysis for real time applications in electrical capacitance tomography M. Neumayer, G. Steiner, D. Watzenig and H. Zangl Towards a-scan imaging via Ultrasonic Vibration Potential measurements P. Guan, M. Wang, H.I. Schlaberg, J. Iqbal Khan and V. Speirs Experimental and theoretical study of the gas–water two phase flow through a conductance multiphase Venturi meter in vertical annular (wet gas) flow A.H.A.M. Hasan and G.P. Lucas Turbulent cooling water discharge into still body of water J. Ali, J. Fieldhouse and C. Talbot
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Regular Papers Engineering Mechanics An advanced method for determination of loss of coolant accident in nuclear power plants R. Mahmoodi, M. Shahriari, A. Zolfaghari and A. Minuchehr
doi:10.1016/S0029-5493(11)00395-5
2013
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Contents/ Nuclear Engineering and Design 241 (2011) iii–v
Optimization of multi-layered metallic shield G. Ben-Dor, A. Dubinsky and T. Elperin Study on modal characteristics of perforated shell using effective Young’s modulus M.J. Jhung and S.O. Yu Consideration of uncertainties in seismic analysis of non-classically damped coupled systems S.K. Tadinada and A. Gupta Critical strains and necking phenomena for different steel sheet specimens under uniaxial loading J. Jeschke, D. Ostermann and R. Krieg Scaling group transformation for MHD boundary-layer flow of a nanofluid past a vertical stretching surface in the presence of suction/injection R. Kandasamy, P. Loganathan and P.P. Arasu
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Material Properties An experimental investigation on bending stiffness and neutral axis depth variation of over-reinforced high strength concrete beams M. Mohammadhassani, M.Z.B. Jumaat, M. Chemrouk, A.A. Maghsoudi, M. Jameel and S. Akib 2060 Stability analysis of SiO2/SiC coatings on matrix graphite for HTR-10 fuel elements Z.-q. Fu, J. Sun, C.-b. Wang, J.-g. Lv, C.-h. Tang, T.-x. Liang and J.-C. Robin 2068 Reactor Engineering Very-Large Eddy Simulation (V-LES) of the flow across a tube bundle M. Labois and D. Lakehal Void measurement using high-resolution gamma-ray computed tomography A. Bieberle, D. Hoppe, E. Schleicher and U. Hampel Thermal hydraulic behaviors during loss of shutdown cooling system at HTS opened under LLDS J.T. Yuan, J.X. Li, L.L. Tong and X.W. Cao Fuel Engineering MARGARET: A comprehensive code for the description of fission gas behavior L. Noirot Mechanical design issues and resolutions of a dual cooled fuel for the OPR-1000 H.-K. Kim, J.-Y. Kim and K.-H. Yoon
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Plant Layout Potential improvements of supercritical recompression CO2 Brayton cycle by mixing other gases for power conversion system of a SFR W.S. Jeong, J.I. Lee and Y.H. Jeong 2128 Reactor Protection Elemental analysis of cement used for radiation shielding by instrumental neutron activation analysis M.E. Medhat and M. Fayez-Hassan
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Core Physics An adaptive finite element approach for neutron transport equation M. Abbassi, A. Zolfaghari, A. Minuchehr and M. Yousefi
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Thermal Hydraulics Group theory transformation for Soret and Dufour effects on free convective heat and mass transfer with thermophoresis and chemical reaction over a porous stretching surface in the presence of heat source/sink R. Kandasamy, T. Hayat and S. Obaidat Sprays in containment: Final results of the SARNET spray benchmark J. Malet, L. Blumenfeld, S. Arndt, M. Babic, A. Bentaib, F. Dabbene, P. Kostka, S. Mimouni, M. Movahed, S. Paci, Z. Parduba, J. Travis and E. Urbonavicius Large Eddy Simulation and the effect of the turbulent inlet conditions in the mixing Tee J.-M. Ndombo and R.J.A. Howard Review and proposal for heat transfer predictions at supercritical water conditions using existing correlations and experiments W. Jäger, V.H. Sánchez Espinoza and A. Hurtado
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Contents/ Nuclear Engineering and Design 241 (2011) iii–v
Analysis of drag and lift coefficient expressions of bubbly flow system for low to medium Reynolds number M.J. Pang and J.J. Wei Experimental and computational investigation of a natural circulation system in Regional Energy Reactor-10 MWth B.-I. Jang, M.H. Kim and G. Jeun
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Safety and Risk Analysis A study on the effects of ESFAS STI modification on the unavailability of ESF actuated components Y.-H. Lee, S.-C. Jang and J.-H. Lee 2224 Determination of rupture frequency for feeders subject to flow accelerated corrosion M. Wang, M. Li, E. Lehockey, X. Duan and M.J. Kozluk 2234 Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code K. Nikitin and A. Manera 2240 Location and sizing of a plant stack: Design study using CFD G. Petrangeli 2248 Passive system reliability analysis using Response Conditioning Method with an application to failure frequency estimation of Decay Heat Removal of PFBR T. Sajith Mathews, A. John Arul, U. Parthasarathy, C. Senthil Kumar, K.V. Subbaiah and P. Mohanakrishnan 2257 Instrumentation and Control Performance evaluation of PFBR wire type sodium leak detectors G. Vijayakumar, K.K. Rajan, B.K. Nashine, S. Chandramouli, K. Madhusoodanan and P. Kalyanasundaram On the speed of response of an FPGA-based shutdown system in CANDU nuclear power plants J. She and J. Jiang
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Environmental Impact Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development A. Abánades, C. García, L. García, A. Escrivá, A. Pérez-Navarro and J. Rosales 2288 Predicting the preferential sites to liquid droplet erosion of the bellows assemblies by CFD H.X. Hu, Y.G. Zheng and C.B. Liu 2295 European new build and fuel cycles in the 21st century F. Roelofs, J. Hart and A. van Heek 2307 New Reactor Concepts Conceptual core design of Advanced Recycling Reactor based on mature technologies K. Ikeda, K.O. Stein, W. Nakazato and M. Mito INPRO economic assessment of the IRIS nuclear reactor for deployment in Brazil O.J.A. Gonçalves Filho Long operation life reactor for lunar surface power M.S. El-Genk and T.M. Schriener
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Waste Management Physico-chemical characterization of clays at Kalpakkam nuclear plant site towards assessment of radioactive waste disposal R. Deepthi Rani and P. Sasidhar 2353 Technical Note Effect of gamma and lead as an additive material on the resistance and strength of concrete D. Rezaei Ochbelagh, S. AzimKhani and H. Gasemzadeh Mosavinejad
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Miscellaneous Survey of dust production in pebble bed reactor cores J.J. Cogliati, A.M. Ougouag and J. Ortensi
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