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                             91 results found
no title author magazine year volume issue page(s) type
1 ADS Fuel Developments in Europe: Results from the EUROTRANS Integrated Project. Delage, F.
 2011
 7 C p. 303-313
11 p.
 article
2 Advanced Fuel Cycle Options Malmbeck, R.
 2011
 7 C p. 93-102
10 p.
 article
3 Advanced Nuclear Reactor Systems – An Indian Perspective Sinha, Ratan Kumar
 2011
 7 C p. 34-50
17 p.
 article
4 Analysis of PHWR LP Turbine Steady State Using RELAP/SCDAP Code Sharma, Brij Mohan
 2011
 7 C p. 367-373
7 p.
 article
5 Application of Accelerators for Nuclear Systems: Accelerator Driven System (ADS) Nema, Pramod Kumar
 2011
 7 C p. 597-608
12 p.
 article
6 Applications of Accelerator Technology and its Relevance to Nuclear Technology Bhandari, R.K.
 2011
 7 C p. 577-588
12 p.
 article
7 A Preliminary Assessment of the Adoption ofInnovative Technologiesinthe Fast Reactor Cycle Technology Development (FaCT)Project in Japan Sato, K.
 2011
 7 C p. 140-145
6 p.
 article
8 A Remotely Operable Facility for Fabrication of Fuel Pins for test Irradiation Prabhu, T.V.
 2011
 7 C p. 222-226
5 p.
 article
9 Arresting the Accidental Discharge of Nuclear Wastes by Modeling the Fuel and Clad Saxena, A.K.
 2011
 7 C p. 512-517
6 p.
 article
10 Austenitic Stainless Steels for Fast Reactors -Irradiation Experiments, Property Evaluation and Microstructural Studies Karthik, V.
 2011
 7 C p. 257-263
7 p.
 article
11 Bioleaching - An Alternate Uranium Ore Processing Technology for India Abhilash,
 2011
 7 C p. 158-162
5 p.
 article
12 Challenges in Manufacture of PFBR Steam Generators Mitra, T.K.
 2011
 7 C p. 317-322
6 p.
 article
13 Challenges of Atomic Energy Regulation in Indian Context Bajaj, S.S.
 2011
 7 C p. 55-59
5 p.
 article
14 Characterisation of High Temperature Phase Stability and Evaluation of Metallurgical Compatibility with SS 304L, of Indigenously Developed Alternate Shielding Material Ferro- Boron for Fast Reactor Applications Raju, S.
 2011
 7 C p. 264-272
9 p.
 article
15 Closed Fuel Cycle System for the FBR Transition from LWR Fukasawa, Tetsuo
 2011
 7 C p. 103-109
7 p.
 article
16 Computational Fluid Dynamic Studies on Gas Entrainment in Fast Breeder Reactors Satpathy, K.
 2011
 7 C p. 333-339
7 p.
 article
17 Computational Intelligent Systems for Prototype Fast Breeder Reactor Jayalal, M.L.
 2011
 7 C p. 589-596
8 p.
 article
18 Contents 2011
 7 C p. iii-vi
nvt p.
 article
19 Current Status and Future Plan of Nuclear Fuel Cycle in Japan, with Focus on Human Resource Development Tanaka, Satoru
 2011
 7 C p. 88-92
5 p.
 article
20 Current Status of Fast Reactors and Future Plans in India Chetal, S.C.
 2011
 7 C p. 64-73
10 p.
 article
21 Design, Development and Testing of a Large Capacity Annular Linear Induction Pump Sharma, Prashant
 2011
 7 C p. 622-629
8 p.
 article
22 Development and Testing of PM Flowmeter with Samarium Cobalt Magnet Assembly Vijayakumar, G
 2011
 7 C p. 630-637
8 p.
 article
23 Development of Helium Leak Testing System and Procedure for testing Welds of Steam Generator Shriwardhankar, R.M.
 2011
 7 C p. 638-644
7 p.
 article
24 Development of Innovative Reactor Assembly Components towards Commercialization of Future FBRs Chellapandi, P.
 2011
 7 C p. 359-366
8 p.
 article
25 Development of Mixed Microbial Granular Biofilms for Denitrification of Concentrated Wastes Mohan, T.V. Krishna
 2011
 7 C p. 507-511
5 p.
 article
26 Development of Pyrochemical Reprocessing for Spent Metal Fuels Nagarajan, K.
 2011
 7 C p. 431-436
6 p.
 article
27 Development of Pyropartitioning Process to Recover Minor Actinide Elements from High Level Liquid Waste Uozumi, K.
 2011
 7 C p. 437-443
7 p.
 article
28 Development of Structural and Steam Generator Materials for Sodium Cooled Fast Reactors Mathew, M.D.
 2011
 7 C p. 250-256
7 p.
 article
29 Developments in Back End of the Fuel Cycle of Indian Thermal Reactors Misra, S.D.
 2011
 7 C p. 474-486
13 p.
 article
30 Effect of Boundary Conditions on Thermohydraulic Behaviour of Clay Buffer used in Nuclear Waste Repository Peter, A. Arul
 2011
 7 C p. 495-501
7 p.
 article
31 Emerging Nuclear Fuel Fabrication Activities in India Jayaraj, R N
 2011
 7 C p. 120-128
9 p.
 article
32 En-Masse Coolant Channel Replacement in Indian PHWR Varghese, Joy P.
 2011
 7 C p. 374-383
10 p.
 article
33 Environmental Radiological Monitoring Around Kalpakkam Venkataraman, S.
 2011
 7 C p. 666-671
6 p.
 article
34 Experience with Dilute Chemical Decontamination in Indian Pressurized Heavy Water Reactors Velmurugan, S.
 2011
 7 C p. 645-649
5 p.
 article
35 Experimental Measurements of Neutron Attenuation in the Advanced Shield Material Ferro Boron in KAMINI Reactor Keshavamurthy, R.S.
 2011
 7 C p. 273-278
6 p.
 article
36 Extraction Chromatography Experiments on Repeated Operation using Engineering Scale Column System Watanabe, Sou
 2011
 7 C p. 449-453
5 p.
 article
37 Extraction of Valuable elements in Spent Nuclear Fuel by using Pyridine Resin 2011
 7 C p. 454-458
5 p.
 article
38 Fast Reactor Fuel Reprocessing Technology: Successes and Challenges Natarajan, R.
 2011
 7 C p. 414-420
7 p.
 article
39 Felsic Volcanic Rocks, a Potential Source of Uranium - An Indian Overview Maithani, P.B.
 2011
 7 C p. 163-168
6 p.
 article
40 Foreword 2011
 7 C p. 1-2
2 p.
 article
41 French SFR R&D Program and Design Activities for SFR Prototype ASTRID Gauche, F.
 2011
 7 C p. 314-316
3 p.
 article
42 High Performance Separation and Supercritical Extraction of Lanthanides and Actinides Datta, Arpita
 2011
 7 C p. 425-430
6 p.
 article
43 Immobilizationof LanthanideOxides Waste fromPyrochemical Process Ahn, B.G.
 2011
 7 C p. 529-533
5 p.
 article
44 Industrial Prospects for the Optimized use of U, Pu and Th for Sustainable Nuclear Energy Deployment Van Den Durpel, Luc
 2011
 7 C p. 21-33
13 p.
 article
45 Inevitability of Nuclear Power in the Asian Region Jain, S.K.
 2011
 7 C p. 5-20
16 p.
 article
46 Investigations on Neutronic Decoupling Phenomenon in Large Nuclear Reactors Singh, Om Pal
 2011
 7 C p. 384-390
7 p.
 article
47 Irradiation Behavior of FBTR Mixed Carbide Fuel at Various Burn-ups Venkiteswaran, C.N.
 2011
 7 C p. 227-233
7 p.
 article
48 Knowledge Management in Fast Reactors Kuriakose, K.K.
 2011
 7 C p. 672-677
6 p.
 article
49 Korean Pyrochemical Process R&D activities Lee, Hansoo
 2011
 7 C p. 391-395
5 p.
 article
50 Laser Applications in Indian Nuclear Power Programme Gupta, P.D.
 2011
 7 C p. 560-576
17 p.
 article
51 Low grade uranium deposits of India – a bane or boon Chaki, Anjan
 2011
 7 C p. 153-157
5 p.
 article
52 Materials and Manufacturing Technologies for Sodium Cooled Fast Reactors and Associated Fuel Cycle: Innovations and Maturity Raj, Baldev
 2011
 7 C p. 186-198
13 p.
 article
53 Materials Development and Corrosion Issues in the Back End of Fuel Cycle Mudali, U. Kamachi
 2011
 7 C p. 468-473
6 p.
 article
54 Materials Development for Indian Nuclear Power Programme: an Industry Perspective Rao, M. Narayana
 2011
 7 C p. 199-204
6 p.
 article
55 Melt Crystallization Process Treatment of LiCl Salt Waste Generated from Electrolytic Reduction Process of Spent Oxide Fuel Cho, Yung-Zun
 2011
 7 C p. 525-528
4 p.
 article
56 Minor Actinide Bearing Fuels: Fabrication and Irradiation Experience in Europe Somers, Joseph
 2011
 7 C p. 169-176
8 p.
 article
57 Nuclear Hybrid Energy Systems: Imperatives, Prospects and Challenges Aumeier, Steven
 2011
 7 C p. 51-54
4 p.
 article
58 Nuclear Rare Metals and their Separation in Advanced ORIENT Cycle Strategy Ozawa, M.
 2011
 7 C p. 421-424
4 p.
 article
59 Nuclear Science and Data Needs for Advanced Nuclear Systems Forrest, R.A.
 2011
 7 C p. 540-552
13 p.
 article
60 Numerical and Experimental Studies on the Performance of Thermal Baffles in Sodium Heated Steam Generator Vinod, V.
 2011
 7 C p. 616-621
6 p.
 article
61 Operating Experience of High Temperature Sodium Loops for Material Testing Shanmugavel, M.
 2011
 7 C p. 609-615
7 p.
 article
62 Overview of Indian Uranium Production Scenario in Coming Decades Gupta, Ramendra
 2011
 7 C p. 146-152
7 p.
 article
63 Performance Assessment of Fuel and Core Structural Materials Irradiated in FBTR Kasiviswanathan, K.V.
 2011
 7 C p. 129-139
11 p.
 article
64 Plastic Deformation in ODS Ferritic Alloys: A 3D Dislocation Dynamics Investigation Gururaj, K.
 2011
 7 C p. 279-285
7 p.
 article
65 Policy Initiatives by the Government of India to Accelerate the Growth of Installed Nuclear Power Capacity in the Coming Years Grover, R B
 2011
 7 C p. 74-78
5 p.
 article
66 Preface 2011
 7 C p. 3-4
2 p.
 article
67 Process Development for Fabrication of Zircaloy–4 Dissolver Assembly for Reprocessing of Spent Nuclear Fuel Tonpe, Sunil
 2011
 7 C p. 459-467
9 p.
 article
68 Pyrochemical Reprocessing of Spent Fuel by Electrochemical Techniques Using Solid Aluminium Cathodes Souček, P.
 2011
 7 C p. 396-404
9 p.
 article
69 Recycle Fuel Fabrication for Closed Fuel Cycle in India Kamath, H.S.
 2011
 7 C p. 110-119
10 p.
 article
70 Remote Leak Sealing of Biological Shield Cooling System of FBTR Manimaran, N.
 2011
 7 C p. 346-350
5 p.
 article
71 Research and Technology Breakthroughs in Nuclear Power for Shaping a Sustainable Low-Carbon Energy Future Carre, Frank
 2011
 7 C p. 60-63
4 p.
 article
72 Self Sloshing of Thermal-Stratification Interface in LMFBR Hot Plenum Tanaka, Nobukazu
 2011
 7 C p. 340-345
6 p.
 article
73 Separation of Thorium and Uranium by Sulfide Method Sato, N.
 2011
 7 C p. 444-448
5 p.
 article
74 Simulation and Integrated Testing of Process Models of PFBR Operator Training Simulator Jayanthi, T.
 2011
 7 C p. 653-659
7 p.
 article
75 Societal Applications of Nuclear Technology in Health Care, Industry and Water Resource Management in India Venugopal, V.
 2011
 7 C p. 553-559
7 p.
 article
76 Sodium Aerosol Studies for Fast Reactor Safety Baskaran, R.
 2011
 7 C p. 660-665
6 p.
 article
77 Some results of Developments and Investigations of Fuel Pins with Metal Fuel for Heterogeneous Core of Fast Reactors of the BN-type Golovchenko, Yu.M.
 2011
 7 C p. 205-212
8 p.
 article
78 Spent Fuel Waste Disposal: Analyses of Model Uncertainty in the MICADO Project Grambow, B.
 2011
 7 C p. 487-494
8 p.
 article
79 State of the Art of Pyroprocessing Technology in Japan Inoue, Tadashi
 2011
 7 C p. 405-413
9 p.
 article
80 Steam Generators for Future Fast Breeder Reactors Nandakumar, R.
 2011
 7 C p. 351-358
8 p.
 article
81 Studies on Novel Matrices for High Level Waste from Fast Reactor Fuel Reprocessing Joseph, Kitheri
 2011
 7 C p. 518-524
7 p.
 article
82 Studies on Steam Pyrolysis of Amides as a Waste Solvent Management Method Dicholkar, Deepak D.
 2011
 7 C p. 534-539
6 p.
 article
83 Technology Breakthrough by Heavy Water Board in Material Support to Indian Nuclear Power Programme Rao, A.L.N.
 2011
 7 C p. 177-185
9 p.
 article
84 The AP1000TM Reactor: Passive Safety and Modular Design Sutharshan, Balendra
 2011
 7 C p. 293-302
10 p.
 article
85 Thermal Analysis of Metallic Fuel for Future FBRs Verma, Vishnu
 2011
 7 C p. 234-249
16 p.
 article
86 Thermochemical Aspects of High Plutonia (44%Pu) MOX Fuel Varamban, S. Vana
 2011
 7 C p. 213-221
9 p.
 article
87 The Status of Generation IV Sodium-Cooled Fast Reactor Technology Development and its Future Project Ichimiya, Masakazu
 2011
 7 C p. 79-87
9 p.
 article
88 Towards a Sustainable Future using Pressure Tube Reactor Technology Duffey, Romney B.
 2011
 7 C p. 286-292
7 p.
 article
89 Treatment of Plastic Waste by Melt Densification- Operational Experience at CWMF Rao, S.V.S.
 2011
 7 C p. 502-506
5 p.
 article
90 Twenty five years of operating experience with the Fast Breeder Test Reactor Kumar, K.V. Suresh
 2011
 7 C p. 323-332
10 p.
 article
91 Validation of CFD and Thermal Hydraulics Codes by Digital Particle Image Velocimetry Singh, R.K.
 2011
 7 C p. 650-652
3 p.
 article
                             91 results found
 
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