| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
ADS Fuel Developments in Europe: Results from the EUROTRANS Integrated Project.
|
Delage, F.
|
|
2011
|
7 |
C |
p. 303-313
11 p.
|
artikel
|
| 2 |
Advanced Fuel Cycle Options
|
Malmbeck, R.
|
|
2011
|
7 |
C |
p. 93-102
10 p.
|
artikel
|
| 3 |
Advanced Nuclear Reactor Systems – An Indian Perspective
|
Sinha, Ratan Kumar
|
|
2011
|
7 |
C |
p. 34-50
17 p.
|
artikel
|
| 4 |
Analysis of PHWR LP Turbine Steady State Using RELAP/SCDAP Code
|
Sharma, Brij Mohan
|
|
2011
|
7 |
C |
p. 367-373
7 p.
|
artikel
|
| 5 |
Application of Accelerators for Nuclear Systems: Accelerator Driven System (ADS)
|
Nema, Pramod Kumar
|
|
2011
|
7 |
C |
p. 597-608
12 p.
|
artikel
|
| 6 |
Applications of Accelerator Technology and its Relevance to Nuclear Technology
|
Bhandari, R.K.
|
|
2011
|
7 |
C |
p. 577-588
12 p.
|
artikel
|
| 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.
|
artikel
|
| 8 |
A Remotely Operable Facility for Fabrication of Fuel Pins for test Irradiation
|
Prabhu, T.V.
|
|
2011
|
7 |
C |
p. 222-226
5 p.
|
artikel
|
| 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.
|
artikel
|
| 10 |
Austenitic Stainless Steels for Fast Reactors -Irradiation Experiments, Property Evaluation and Microstructural Studies
|
Karthik, V.
|
|
2011
|
7 |
C |
p. 257-263
7 p.
|
artikel
|
| 11 |
Bioleaching - An Alternate Uranium Ore Processing Technology for India
|
Abhilash,
|
|
2011
|
7 |
C |
p. 158-162
5 p.
|
artikel
|
| 12 |
Challenges in Manufacture of PFBR Steam Generators
|
Mitra, T.K.
|
|
2011
|
7 |
C |
p. 317-322
6 p.
|
artikel
|
| 13 |
Challenges of Atomic Energy Regulation in Indian Context
|
Bajaj, S.S.
|
|
2011
|
7 |
C |
p. 55-59
5 p.
|
artikel
|
| 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.
|
artikel
|
| 15 |
Closed Fuel Cycle System for the FBR Transition from LWR
|
Fukasawa, Tetsuo
|
|
2011
|
7 |
C |
p. 103-109
7 p.
|
artikel
|
| 16 |
Computational Fluid Dynamic Studies on Gas Entrainment in Fast Breeder Reactors
|
Satpathy, K.
|
|
2011
|
7 |
C |
p. 333-339
7 p.
|
artikel
|
| 17 |
Computational Intelligent Systems for Prototype Fast Breeder Reactor
|
Jayalal, M.L.
|
|
2011
|
7 |
C |
p. 589-596
8 p.
|
artikel
|
| 18 |
Contents
|
|
|
2011
|
7 |
C |
p. iii-vi
nvt p.
|
artikel
|
| 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.
|
artikel
|
| 20 |
Current Status of Fast Reactors and Future Plans in India
|
Chetal, S.C.
|
|
2011
|
7 |
C |
p. 64-73
10 p.
|
artikel
|
| 21 |
Design, Development and Testing of a Large Capacity Annular Linear Induction Pump
|
Sharma, Prashant
|
|
2011
|
7 |
C |
p. 622-629
8 p.
|
artikel
|
| 22 |
Development and Testing of PM Flowmeter with Samarium Cobalt Magnet Assembly
|
Vijayakumar, G
|
|
2011
|
7 |
C |
p. 630-637
8 p.
|
artikel
|
| 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.
|
artikel
|
| 24 |
Development of Innovative Reactor Assembly Components towards Commercialization of Future FBRs
|
Chellapandi, P.
|
|
2011
|
7 |
C |
p. 359-366
8 p.
|
artikel
|
| 25 |
Development of Mixed Microbial Granular Biofilms for Denitrification of Concentrated Wastes
|
Mohan, T.V. Krishna
|
|
2011
|
7 |
C |
p. 507-511
5 p.
|
artikel
|
| 26 |
Development of Pyrochemical Reprocessing for Spent Metal Fuels
|
Nagarajan, K.
|
|
2011
|
7 |
C |
p. 431-436
6 p.
|
artikel
|
| 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.
|
artikel
|
| 28 |
Development of Structural and Steam Generator Materials for Sodium Cooled Fast Reactors
|
Mathew, M.D.
|
|
2011
|
7 |
C |
p. 250-256
7 p.
|
artikel
|
| 29 |
Developments in Back End of the Fuel Cycle of Indian Thermal Reactors
|
Misra, S.D.
|
|
2011
|
7 |
C |
p. 474-486
13 p.
|
artikel
|
| 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.
|
artikel
|
| 31 |
Emerging Nuclear Fuel Fabrication Activities in India
|
Jayaraj, R N
|
|
2011
|
7 |
C |
p. 120-128
9 p.
|
artikel
|
| 32 |
En-Masse Coolant Channel Replacement in Indian PHWR
|
Varghese, Joy P.
|
|
2011
|
7 |
C |
p. 374-383
10 p.
|
artikel
|
| 33 |
Environmental Radiological Monitoring Around Kalpakkam
|
Venkataraman, S.
|
|
2011
|
7 |
C |
p. 666-671
6 p.
|
artikel
|
| 34 |
Experience with Dilute Chemical Decontamination in Indian Pressurized Heavy Water Reactors
|
Velmurugan, S.
|
|
2011
|
7 |
C |
p. 645-649
5 p.
|
artikel
|
| 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.
|
artikel
|
| 36 |
Extraction Chromatography Experiments on Repeated Operation using Engineering Scale Column System
|
Watanabe, Sou
|
|
2011
|
7 |
C |
p. 449-453
5 p.
|
artikel
|
| 37 |
Extraction of Valuable elements in Spent Nuclear Fuel by using Pyridine Resin
|
|
|
2011
|
7 |
C |
p. 454-458
5 p.
|
artikel
|
| 38 |
Fast Reactor Fuel Reprocessing Technology: Successes and Challenges
|
Natarajan, R.
|
|
2011
|
7 |
C |
p. 414-420
7 p.
|
artikel
|
| 39 |
Felsic Volcanic Rocks, a Potential Source of Uranium - An Indian Overview
|
Maithani, P.B.
|
|
2011
|
7 |
C |
p. 163-168
6 p.
|
artikel
|
| 40 |
Foreword
|
|
|
2011
|
7 |
C |
p. 1-2
2 p.
|
artikel
|
| 41 |
French SFR R&D Program and Design Activities for SFR Prototype ASTRID
|
Gauche, F.
|
|
2011
|
7 |
C |
p. 314-316
3 p.
|
artikel
|
| 42 |
High Performance Separation and Supercritical Extraction of Lanthanides and Actinides
|
Datta, Arpita
|
|
2011
|
7 |
C |
p. 425-430
6 p.
|
artikel
|
| 43 |
Immobilizationof LanthanideOxides Waste fromPyrochemical Process
|
Ahn, B.G.
|
|
2011
|
7 |
C |
p. 529-533
5 p.
|
artikel
|
| 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.
|
artikel
|
| 45 |
Inevitability of Nuclear Power in the Asian Region
|
Jain, S.K.
|
|
2011
|
7 |
C |
p. 5-20
16 p.
|
artikel
|
| 46 |
Investigations on Neutronic Decoupling Phenomenon in Large Nuclear Reactors
|
Singh, Om Pal
|
|
2011
|
7 |
C |
p. 384-390
7 p.
|
artikel
|
| 47 |
Irradiation Behavior of FBTR Mixed Carbide Fuel at Various Burn-ups
|
Venkiteswaran, C.N.
|
|
2011
|
7 |
C |
p. 227-233
7 p.
|
artikel
|
| 48 |
Knowledge Management in Fast Reactors
|
Kuriakose, K.K.
|
|
2011
|
7 |
C |
p. 672-677
6 p.
|
artikel
|
| 49 |
Korean Pyrochemical Process R&D activities
|
Lee, Hansoo
|
|
2011
|
7 |
C |
p. 391-395
5 p.
|
artikel
|
| 50 |
Laser Applications in Indian Nuclear Power Programme
|
Gupta, P.D.
|
|
2011
|
7 |
C |
p. 560-576
17 p.
|
artikel
|
| 51 |
Low grade uranium deposits of India – a bane or boon
|
Chaki, Anjan
|
|
2011
|
7 |
C |
p. 153-157
5 p.
|
artikel
|
| 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.
|
artikel
|
| 53 |
Materials Development and Corrosion Issues in the Back End of Fuel Cycle
|
Mudali, U. Kamachi
|
|
2011
|
7 |
C |
p. 468-473
6 p.
|
artikel
|
| 54 |
Materials Development for Indian Nuclear Power Programme: an Industry Perspective
|
Rao, M. Narayana
|
|
2011
|
7 |
C |
p. 199-204
6 p.
|
artikel
|
| 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.
|
artikel
|
| 56 |
Minor Actinide Bearing Fuels: Fabrication and Irradiation Experience in Europe
|
Somers, Joseph
|
|
2011
|
7 |
C |
p. 169-176
8 p.
|
artikel
|
| 57 |
Nuclear Hybrid Energy Systems: Imperatives, Prospects and Challenges
|
Aumeier, Steven
|
|
2011
|
7 |
C |
p. 51-54
4 p.
|
artikel
|
| 58 |
Nuclear Rare Metals and their Separation in Advanced ORIENT Cycle Strategy
|
Ozawa, M.
|
|
2011
|
7 |
C |
p. 421-424
4 p.
|
artikel
|
| 59 |
Nuclear Science and Data Needs for Advanced Nuclear Systems
|
Forrest, R.A.
|
|
2011
|
7 |
C |
p. 540-552
13 p.
|
artikel
|
| 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.
|
artikel
|
| 61 |
Operating Experience of High Temperature Sodium Loops for Material Testing
|
Shanmugavel, M.
|
|
2011
|
7 |
C |
p. 609-615
7 p.
|
artikel
|
| 62 |
Overview of Indian Uranium Production Scenario in Coming Decades
|
Gupta, Ramendra
|
|
2011
|
7 |
C |
p. 146-152
7 p.
|
artikel
|
| 63 |
Performance Assessment of Fuel and Core Structural Materials Irradiated in FBTR
|
Kasiviswanathan, K.V.
|
|
2011
|
7 |
C |
p. 129-139
11 p.
|
artikel
|
| 64 |
Plastic Deformation in ODS Ferritic Alloys: A 3D Dislocation Dynamics Investigation
|
Gururaj, K.
|
|
2011
|
7 |
C |
p. 279-285
7 p.
|
artikel
|
| 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.
|
artikel
|
| 66 |
Preface
|
|
|
2011
|
7 |
C |
p. 3-4
2 p.
|
artikel
|
| 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.
|
artikel
|
| 68 |
Pyrochemical Reprocessing of Spent Fuel by Electrochemical Techniques Using Solid Aluminium Cathodes
|
Souček, P.
|
|
2011
|
7 |
C |
p. 396-404
9 p.
|
artikel
|
| 69 |
Recycle Fuel Fabrication for Closed Fuel Cycle in India
|
Kamath, H.S.
|
|
2011
|
7 |
C |
p. 110-119
10 p.
|
artikel
|
| 70 |
Remote Leak Sealing of Biological Shield Cooling System of FBTR
|
Manimaran, N.
|
|
2011
|
7 |
C |
p. 346-350
5 p.
|
artikel
|
| 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.
|
artikel
|
| 72 |
Self Sloshing of Thermal-Stratification Interface in LMFBR Hot Plenum
|
Tanaka, Nobukazu
|
|
2011
|
7 |
C |
p. 340-345
6 p.
|
artikel
|
| 73 |
Separation of Thorium and Uranium by Sulfide Method
|
Sato, N.
|
|
2011
|
7 |
C |
p. 444-448
5 p.
|
artikel
|
| 74 |
Simulation and Integrated Testing of Process Models of PFBR Operator Training Simulator
|
Jayanthi, T.
|
|
2011
|
7 |
C |
p. 653-659
7 p.
|
artikel
|
| 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.
|
artikel
|
| 76 |
Sodium Aerosol Studies for Fast Reactor Safety
|
Baskaran, R.
|
|
2011
|
7 |
C |
p. 660-665
6 p.
|
artikel
|
| 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.
|
artikel
|
| 78 |
Spent Fuel Waste Disposal: Analyses of Model Uncertainty in the MICADO Project
|
Grambow, B.
|
|
2011
|
7 |
C |
p. 487-494
8 p.
|
artikel
|
| 79 |
State of the Art of Pyroprocessing Technology in Japan
|
Inoue, Tadashi
|
|
2011
|
7 |
C |
p. 405-413
9 p.
|
artikel
|
| 80 |
Steam Generators for Future Fast Breeder Reactors
|
Nandakumar, R.
|
|
2011
|
7 |
C |
p. 351-358
8 p.
|
artikel
|
| 81 |
Studies on Novel Matrices for High Level Waste from Fast Reactor Fuel Reprocessing
|
Joseph, Kitheri
|
|
2011
|
7 |
C |
p. 518-524
7 p.
|
artikel
|
| 82 |
Studies on Steam Pyrolysis of Amides as a Waste Solvent Management Method
|
Dicholkar, Deepak D.
|
|
2011
|
7 |
C |
p. 534-539
6 p.
|
artikel
|
| 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.
|
artikel
|
| 84 |
The AP1000TM Reactor: Passive Safety and Modular Design
|
Sutharshan, Balendra
|
|
2011
|
7 |
C |
p. 293-302
10 p.
|
artikel
|
| 85 |
Thermal Analysis of Metallic Fuel for Future FBRs
|
Verma, Vishnu
|
|
2011
|
7 |
C |
p. 234-249
16 p.
|
artikel
|
| 86 |
Thermochemical Aspects of High Plutonia (44%Pu) MOX Fuel
|
Varamban, S. Vana
|
|
2011
|
7 |
C |
p. 213-221
9 p.
|
artikel
|
| 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.
|
artikel
|
| 88 |
Towards a Sustainable Future using Pressure Tube Reactor Technology
|
Duffey, Romney B.
|
|
2011
|
7 |
C |
p. 286-292
7 p.
|
artikel
|
| 89 |
Treatment of Plastic Waste by Melt Densification- Operational Experience at CWMF
|
Rao, S.V.S.
|
|
2011
|
7 |
C |
p. 502-506
5 p.
|
artikel
|
| 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.
|
artikel
|
| 91 |
Validation of CFD and Thermal Hydraulics Codes by Digital Particle Image Velocimetry
|
Singh, R.K.
|
|
2011
|
7 |
C |
p. 650-652
3 p.
|
artikel
|
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