Annals of Nuclear Energy
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
Table of contents
- 2625
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Thermal hydraulic performance analysis of a double tube bundle steam generator for a liquid metal reactorKim, Eui-Kwang / Baek, Byung-Joon et al. | 2011
- 2634
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Loss of flow accident and its mitigation measures for nuclear systems with SCWR-MXu, Zhihong / Hou, Dong / Fu, Shengwei et al. | 2011
- 2645
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Thermo-hydraulic reasons for the Local Power Range Monitor (LPRM) spikingGavilán Moreno, Carlos J. et al. | 2011
- 2653
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Steady-state neutronic analysis of converting the UK CONSORT reactor for ADS experimentsOwen, Hywel / Gill, Matthew / Chambers, Trevor et al. | 2011
- 2661
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Reformation of hazardous wastes into useful supporting materials for fast reactor fuelsOsaka, Masahiko / Miwa, Shuhei / Tanaka, Kosuke et al. | 2011
- 2667
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Determination of Tehran Research Reactor power by 16N gamma detectionArmozd, Hamid Reza / Gharib, Morteza / Afarideh, Hossein et al. | 2011
- 2673
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MgO single-crystal as an efficient thermal neutron filterAdib, M. / Habib, N. / Bashter, I. et al. | 2011
- 2680
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A Hybrid Transport Point-Kinetic method for simulating source transients in subcritical systemsPicca, Paolo / Furfaro, Roberto / Ganapol, Barry D. et al. | 2011
- 2689
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Plutonium isotopic composition of high burnup spent fuel discharged from light water reactorsNakano, Yoshihiro / Okubo, Tsutomu et al. | 2011
- 2698
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CORE SIM: A multi-purpose neutronic tool for research and educationDemazière, Christophe et al. | 2011
- 2719
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Determination and calculation of gamma and neutron shielding characteristics of concretes containing different hematite proportionsGencel, Osman / Bozkurt, Ahmet / Kam, Erol et al. | 2011
- 2724
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Sampling based uncertainty analysis of station blackout in PSB VVER integral test facilityDubey, S.K. / Rao, R.S. / Sengupta, S. et al. | 2011
- 2734
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A three-dimensional thermal and fluid dynamics analysis of a gas cooled subcritical fast reactor driven by a D–T fusion neutron sourceAngelo, G. / Andrade, D.A. / Angelo, E. et al. | 2011
- 2742
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An acceleration technique for 2D MOC based on Krylov subspace and domain decomposition methodsZhang, Hongbo / Wu, Hongchun / Cao, Liangzhi et al. | 2011
- 2752
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Photoneutron production and backscattering in high density concretes used for radiation therapy shieldingMesbahi, Asghar / Azarpeyvand, Ali-Asghar / Shirazi, Alireza et al. | 2011
- 2757
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Three-dimensional neutronic calculations for a fusion breeder APEX reactor using some librariesGünay, Mehtap / Şarer, Başar / Çelik, Yurdunaz et al. | 2011
- 2762
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Analysis of hydrogen risk mitigation with passive autocatalytic recombiner system in CPR1000 NPP during a hypothetical station blackoutHuang, X.G. / Yang, Y.H. / Zhang, S.X. et al. | 2011
- 2770
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Bubble viscosity effect on internal circulation within the bubble rising due to buoyancy using the level set methodAnsari, M.R. / Nimvari, M.E. et al. | 2011
- 2779
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Analysis of laminar to turbulent transition of pulsating flow in ocean environment with energy gradient methodYan, B.H. et al. | 2011
- 2787
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An Interval Bound Algorithm of optimizing reactor core loading pattern by using reactivity interval schemaGong, Zhaohu / Wang, Kan / Yao, Dong et al. | 2011
- 2797
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Model development and simulation of transient behavior of helium turbine systemXie, Heng et al. | 2011
- 2806
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Analysis of shape isomer yields of heavy elements in the framework of dynamical-statistical modelEslamizadeh, H. et al. | 2011
- 2810
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An efficient technique for the point reactor kinetics equations with Newtonian temperature feedback effectsNahla, Abdallah A. et al. | 2011
- 2818
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The Davidson method as an alternative to power iterations for criticality calculationsSubramanian, C. / Van Criekingen, S. / Heuveline, V. et al. | 2011
- 2824
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An experimental study of the shielding characteristics of the dwelling house building materials against gamma radiations in the Central Region of SyriaAlbarhoum, M. / Soufan, A.H. / Mustafa, H. et al. | 2011
- 2830
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Impact of cross section libraries on CASMO-4E and CASMO-4 resultsRantamäki, K.M. / Häkkinen, S. / Anttila, M. et al. | 2011
- 2836
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Reactivity feedback coefficients of a low enriched uranium fuelled material test research reactor at end-of-lifeMuhammad, Farhan et al. | 2011
- 2840
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Burnup management simulator for small and medium sized reactorsKrishna Kumar, P.T. / Takeda, Toshikazu et al. | 2011
- 2843
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Hot point detection methodGandini, A. et al. | 2011
- 2848
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Identification of an equivalent electrical model to a natural circulation BWR core modelValle-Hernández, Julio / Espinosa-Paredes, Gilberto / Morales-Sandoval, Jaime B. et al. | 2011
- 2859
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Calculation of the power distribution in the fuel rods of the low power research reactor using the MCNP4C codeDawahra, S. / Khattab, K. et al. | 2011
- 2863
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Comment on the paper “Post-Shutdown decay power and radionuclide inventories in the discharged fuels of HEU and potential LEU miniature neutron source reactors” by Mirza et al. [Ann. Nucl. Energy 37 (2010) 701–706]Chamgordani, H.Kh. / Mostajaboddavati, S.M. / Sichani, B.T. et al. | 2011
- 2865
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Response to: Comment on the paper “Post-Shutdown decay power and radionuclide inventories in the discharged fuels of HEU and potential LEU miniature neutron source reactors” by Mirza, S.M., Khan, A., Mirza N.M. [Ann. Nucl. Energy 37 (2010) 701–706]Mirza, Nasir M. et al. | 2011
- IFC
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Editorial board| 2011