Thorium Energy Conference 2015
Welcome to “ThEC15 in Mumbai”!
Summary
How will we power the world with clean, safe, affordable, scalable, resilient energy and what does 300 participants, 127 papers, 46 speakers, 30 nationalities, 26 sponsors, 4 hosts, a reactor visit have to do with it?
Science Magazine wrote Thorium As Nuclear's New Frontier after attending and conducting interviews at ThEC15 in Mumbai.
India has learned how to master the Thorium Fuel Cycle. Through persistent research and development efforts they have built institutions, facilities and expertise that today can't be found anywhere else in the world. ThEC15 was held in Mumbai and hosted by the Government of India organizations BARC and NPCIL together with HBNI and IThEO to learn more and get to know the people behind it.
...what scientists, typically in the western world, are doing in computers is done in real experiments here in India
-Dr. J. Krepel, PSI, Switzerland
...it is for the Thorium community to emphasize that it should be done right away, no delay!
-Dr. S. Banerjee, BARC, India
On Sunday, the conference attendees were invited to a welcome reception and dinner at the Royal Orchid in Navi Mumbai. The official program started on Monday with an inaugural session, where the leaders of the host institutions – BARC, HBNI and NPCIL – addressed the attendees. The inaugural session was concluded with the presentation of the first Thorium Energy Prize, given to Mr. R.K. Sinha, former Chairman of the Atomic Energy Commission of India. After the prize ceremony, Mr. Sinha inaugurated the Exhibition area, where conference sponsors had their booths, and all poster sessions took place.
Enthusiastic school kids from Mumbai queued to visit the exhibition center at ThEC15 to learn more about Thorium Energy.
The rest of the Monday program was dedicated to addressing Thorium Energy in the context of sustainability, as well as to start a series of national overviews. From Tuesday afternoon onwards, the presentations went deeper into technical detail. On Thursday, the last day of presentations, the entire day was dedicated to the Indian Thorium Energy program. At the end of the day, it was time for a panel discussion and closing of the conference.
On Friday, the attendees were given a special opportunity to visit the Tarapur reactor outside of Mumbai. Due to strict security, there is no photo material or details available from the visit. However, we invite you to see a documentary prepared by the National Geographic that visits the same reactor.
On this website, we have gathered all available conference material. It starts with the presentations, in the order they were presented. Provided that the speaker has given allowance, we have included a link to presentation slides. Presentations are followed by posters, grouped by subject area. Again, a link to the entire paper is provided if allowed by the author. As a new feature, we have included an interview section, where we publish selected interviews conducted during the conference. The Thorium Energy Prize was awarded for the first time at ThEC15, and is devoted its own section on this website.
Interviews
Benjamin Soon explains the importance of Thorium Energy to the world, Flibe Energy’s goals, the liquid fluoride thorium reactor (LFTR) technology, challenges in the path towards Thorium Energy deployment, and geopolitics
Anil Kakodkar says thorium and solar is the ideal mix for India.
Saleem Drera at Thor Energy aims to cut the time to market for thorium fuels.
An interview with the esteemed scientist Professor Srikumar Banerjee, former Chairman of the Atomic Energy Commission of India.
Several interviews of key persons were conducted during the conference. They will be published gradually, so keep visiting the page, or follow us on Twitter and Facebook to find out when a new interview is released!
Prize
The first Thorium Energy Prize was awarded at ThEC15. It was given to Mr. R.K. Sinha, then Chairman of the Atomic Energy Commission, for the achievements made in the Indian Thorium Energy Program.
A lifetime's Thorium Energy supply in your hand
Thorium is the gateway to powering India’s economy
For major achievements in the field of Thorium Energy, the International Thorium Energy Organization, IThEO, is pleased to confer the Thorium Energy Prize to the Department of Atomic Energy, Government of India, for successful development of technologies for all aspects of thorium fuel cycle right from exploration, mining, fuel fabrication, irradiation in reactors, reprocessing and waste management, this is a major step towards large scale deployment of thorium in power reactors
-Mr Norlin, President IThEO
In the next conference, ThE Prize will be handed out to the next person, who has made significant contributions to the field.
ThE Prize represents the fact that a lifetime's energy need of each one of us on this planet can be generated from an amount of thorium that fits in the palm of your hand. It's a gift from 'Mother Earth', handed for us to reach - what we need to do is enable research and development efforts to make Thorium Energy a reality.
Nuclear in India
ThEC15 attendees were given a unique opportunity to visit the Tarapur Atomic Power Station (TAPS), located in Tarapur, Maharashtra. With a total capacity of 1400 MW, Tarapur is the largest nuclear power station in India. The facility is operated by the Nuclear Power Corporation of India Limited (NPCIL).
The conference attendees visited the the newer reactors, TAPS 3 and 4. Due to security, no pictures or videos were allowed during the visit. We would, however, like to encourage you to see a great documentary by National Geographic of the Tarapur facilities.
The Tarapur Atomic Power Station was initially constructed with two Boiling water reactor (BWR) units by Bechtel and GE under an agreement between India, the United States, and the International Atomic Energy Agency (IAEA). Units 1 and 2 were brought online for commercial operation on 28th of October 1969. These were the first of their kind in Asia. More recently, an additional two Pressurised heavy water reactor (PHWR) units of 540 MW each were constructed by L & T and Gammon India. Unit 3 was brought online for commercial operation on 18 August 2006, and unit 4 on 12 September 2005.
Talks
Here you can find all the speakers of ThEC15, in the order they presented. The first section covers the inaugural ceremony. Provided that the speaker has given allowance, you can also click to see the presentation slides.
Program
Philosophy of future ready thorium reactor designs by R. K. Sinha, Chairman Atomic Energy Commission, India
Harnessing thorium for nuclear power: challenges ahead by Anil Kakodkar, ex. Chairman Atomic Energy Commission, India
Nuclear Power from Thorium – Different Approaches by S. Banerjee, ex. Chairman Atomic Energy Commission, India
Indian nuclear power programme – role of thorium and the challenges ahead by P. K. Vijayan, Director of Reactor Design and Development Group BARC, India
Thorium research and development in Turkey by Görkem Gungor, Ministry of Energy and Natural
Resources, Turkey
A Canadian Perspective on Progress in Thorium R&D: Towards Sustainability by Robert Speranzini, Head, National and International Collaborations CNL, Canada
Resources of thorium toward alternatives power plant in Indonesia: A concept of Implementation by Yudiutomo Imardjoko, CEO Indonesian Nuclear Company, Indonesia
The evolutionary adoption of thorium beginning with its application in niche LWR fuels by Saleem Drera, VP R&D Thor Energy, Norway
Feasibility Study of a Pilot Scale Molten Salt Reactor Demonstration by Rory O’Sullivan, co-founder EPD, UK
LFTR: In search of the Ideal Pathway to Thorium Utilization-Development Program & Current Status by Benjamin Soon, Executive Director Southeast Asia Flibe Energy, USA
Static Fuel Molten Salt Reactors - Simpler, Cheaper and Safer by Ian Scott, founder Moltex Energy, UK
SAMOFAR – A Paradigm Shift in Reactor Safety with the Molten Salt Fast Reactor by Jiri Krepel, PSI, Switzerland
Thorium Utilization in Fast Breeder Reactors and in Cross-Progeny Fuel Cycles by Balraj Sehgal, KTH, Sweden
Technology Considerations for Deployment of Thorium Power Reactors by Matthias Krause, IAEA, Austria
Canadian Nuclear Laboratories’ Thoria Road Map Project by Bhaskar Sur, Canadian Nuclear Laboratories, Canada
A walkthrough of the Copenhagen Atomics Waste Burner design by Thomas Jam Pedersen, Copenhagen Atomics, Denmark
Performance of Energy Multiplier Module (EM2) with Long-Burn Thorium Fuel Cycle by Puja Gupta, General Atomics, India
Feasibility and Deployment Strategy of Water Cooled Thorium Breeder Reactor by Naoyuki Takaki, Tokyo City Uni., Japan
Power flattening study of Ultra-long Cycle Fast Reactor (UCFR) core by Taewoo Tak, UNIST, South Korea
Developmental activities related to thorium purification and metal production by S. B. Roy, BARC, India
Thermo-Physical Properties and Phase Transformation behavior of Thorium based Alloys
and Oxides by G. K. Dey, BARC, India
Thermophysical and thermochemical evaluation of prospective Th-fuels for advanced
Reactors by B. N. Jagatap, BARC, India
Thorium reserves: potential for power generation, exploration and mining by R. N. Patra, CMD IREL, India
Papers
Here you can find the 127 posters presented during the conference. We have grouped them according to subject area. Provided that the author has given allowance, we have included a link to the full paper.
Reactor Physics, Nuclear Data and Radiological Physics
Improvement in estimation of distribution algorithm (EDA) for fuel loading pattern optimization in AHWR
A. Thakur a,*, B. Singha, A. Guptaa, V. Duggalb, K. Bhattb and P. D. Krishnania
Reactor Physics Design Divisiona, Computer Divisionb, Bhabha Atomic Research, India
Burn up and flux profile dependent temperature distribution in thoria pellet
Anuj Kumar Deo, Subrata Bera and A. J. Gaikwad
Nuclear Safety Analysis Division, AERB, India
A simplified burnup calculation strategy with refueling in static Molten Salt Reactor
A. K. Srivastava, Anurag Gupta, P. D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
3D space time analysis of anticipated transient without scram in CHTR with fuel temperature feedback
D.K. Dwivedi*, Anurag Gupta, P.D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
Studies for performing void reactivity measurements in AHWR-CF with fuel clusters of Initial and Equilibrium core of AHWR
Neelima Prasad* and P.D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
Validation of multipoint kinetics model against 3D TRIKIN code
Rakesh Kumar, S. K. Pradhan, Obaidurrahman K.* and Avinash. J. Gaikwad
Nuclear Safety Analysis Division, Atomic Energy Regulatory Board, India
Investigations on neutronic coupling aspects of Thorium fueled AHWR code
Obaidurrahman K. and Avinash. J. Gaikwad
Nuclear Safety Analysis Division, Atomic Energy Regulatory Board, India
Turkey’s Thorium strategy: Devising a new nuclear path in a developing state
Eyup Ersoya, Serhan Unalb
aBilkent University, Department of International Relations, 06800, Ankara, Turkey
bMiddle East Technical University, Department of International Relations, 06800,
Ankara, Turkey; Turkish Energy Foundation, Turkey
Xenon dynamics in AHWR-LEU with coolant density and fuel temperature feedback
Arindam Chakraborty, Amit Thakur, Baltej Singh and P.D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
A dynamic analysis of circulating fuel reactor with zero dimensional modeling
Indrajeet Singh, Anurag Gupta and P.D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
Reactor Physics Experiments with Thorium based Clusters in AHWR - Critical Facility
Kapil Deo*, Neelima Prasad, A.K. Mallick, Rajeev Kumar, Sudipta Samanta and
P.D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
Power flattening study for UCFR
Taewoo Tak and Deokjung Lee
Ulsan National Institute of Science and Technology, Korea
Effect of flooding of annulus space between CT and PT with coolant or moderator on reactor physics parameters of AHWR-LEU core
Vishal Bharti*, Arindam Chakraborty, Amit Thakur, Baltej Singh and P.D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
Comparison study of AHWR-LEU equilibrium core using two different diffusion theory codes
A. Thakur a*, A. K. Mallicka, B. Singha, H. P. Guptab, V. Bhartia, N. Pushpama and P. D.
Krishnania
aReactor Physics Design Division, bRaja Ramanna Fellow
Bhabha Atomic Research Centre, India
Generating one group cross-section for isotope depletion and generation calculation for Thorium fuel
Amit Rajora*, Gaurav Agarwal, Manish Kaushal, Sherly Ray, A. S. Pradhan, Suma R.
Nair, S. G. Ghadge
Reactor Physics & Shielding Section, RSA, Nuclear Power Corporation of India Limited, India
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Feasibility to produce Uranium-233 from Thorium in PHWR
Gaurav Agarwal*, Surendra Mishra, Sherly Ray, A. S. Pradhan, Suma. R. Nair, S. G.
Ghadge
Reactor Physics & Shielding Section, RSA, Nuclear Power Corporation of India Limited, India
Optimization study for loading of Thorium bundles in 700 MWe PHWR initial core
Surendra Mishra*, Sherly Ray, A. S. Pradhan, Suma. R. Nair, S. G. Ghadge
Reactor Physics & Shielding Section, RSA, Nuclear Power Corporation of India Limited, India
Evolution of actinides in ThO2 blanket of Prototype Fast Breeder Reactor
Abhitab Bachchan*, A. Riyas, K. Devan and P. Puthiyavinayagam
Core Design Group, Indira Gandhi Centre for Atomic Research, India
Energywise contributions of Th, Pu& U isotopes to the reactivity feedbacks of (Th-LEU) fuelled AHWR
Anindita Sarkar*, Umasankari Kannan and P.D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
Investigations on production of U233 using few pin thoria in existing PHWRs
Ishi Jain*, M.P.S. Fernando, Suma R. Nair, S.G. Ghadge
Nuclear Power Corporation of India Ltd., India
Core follow up to irradiate pure thoria along with natural uranium bundles in Indian PHWRs
Suresh Kandpal*, Abhishek Chakraborty, M.P.S. Fernando, Suma R. Nair, S.G. Ghadge
Nuclear Power Corporation of India Ltd., India
LORA analysis using Thorium in 220 MWe PHWR fuel
Manish Raj*, M.P.S. Fernando, Suma Nair, S.G. Ghadge
Nuclear Power Corporation of India Ltd., India
Recent Measurements with the NIFFTE Fission TPC and the Potential to Advance Thorium Fueled Reactors
Rusty Towell
Abilene Christian University, USA
Radiation dose rate mapping of molten active fluoride salt loop at UED, BARC
Tanmay Sarkara*, Pradeep Bhargavaa, Ananta Bb, A.K. Srivastavab and R.K.B. Yadavc
aHealth Physics Division, bReactor Engineering Division, cRadiation Safety Systems
Division, Bhabha Atomic Research Centre, India
A total absorption gamma spectroscopy (TAGS) setup at VECC, KOLKATA
G. Mukherjee, BalaramDey, S. Mukhopadhyay, Deepak Pandit, Surajit Pal, H. Pai and
S.R. Banerjee
Experimental Nuclear Physics Division, Variable Energy Cyclotron Centre, India
Computational study of neutronic performance of the CANDU 6 reactor core fuelled with (ThO2+UO2)
Zohreh Gholamzadeha*, Seyed Amirhossein Feghhib, AtyehJoze-Vaziria, Masoumeh
Alizadeha and Seyed Mohammad Mirvakilia
aReactor Research School, Nuclear Science and Technology Research Institute, Iran,
bDepartment of Radiation Application, Shahid Beheshti University, G.C, Iran
Radiological impact assessment for near surface disposal of Th232
Faby Sunny* and Manish Chopra
Radiation Safety Systems Division, Bhabha Atomic Research Centre, India
Continuous Irradiation of Thorium in Equilibrium core of Standard PHWRs
G. Raja Rao, R. Padhy and M. V. Parikh
Reactor Physics section, Kakrapar Atomic Power Station, NPCIL, India
Materials
Thermophysical properties of thorium compounds from first principles
Vinayak Mishraa,* and Shashank Chaturvedia
Computational Analysis Division, Bhabha Atomic Research Centre, India
Evaluation of Higher K-modes of AHWR-LEU core and Estimation of Neutron Flux at In-core Detector Locations
Sudipta Samantaa, K.P. Singhb and Umasankari Kannana
aReactor Physics Design Division, bMP&RThS, Bhabha Atomic Research Centre, India
Geological framework and thorium resources exploration condition of Georgia (The Caucasus)
Avtandil Okrostsvaridzea*, David Bluashvilib , Nona Gagnidzea
aFaculty of Natural Sciences and Engineering, Ilia state University, Georgia
bFaculty of Geology and Mining, Georgian Technical University, Georgia
Microstructural evolution and thermophysical property evaluation of Th-U alloys
Santanu Das, Raj Kumar, Santu Kaity, Joydipto Bannerjee, S B Roy, G P Chaudhari,
B S S Daniel
Integrated Fuel Fabrication Facility, Uranium Extraction Division, Bhabha Atomic
Research Centre, India
Abstract I Paper
Thermodynamic modelling of corrosion of structural metals by molten salts - effect of sacrificial metals
J. Turner, H. Lambert, T. Abram, Ian Scott
Manchester University, Moltex Energy LLP
Alpha autoradiography studies on thoria-plutonia experimental fuel for Pu Homogeneity
K.V. Vrinda Devi*, P. S. Somayajulu, J.N. Dubey, I.H. Shaikh, S.D. Raut, Jyoti Gupta,
K.B. Khan and Arun Kumar
Radiometallurgy Division, Bhabha Atomic Research Centre, India
Romanian Irradiation Experiment on AHWR Type Fuel Elements Containing Mixed Oxide of Thorium and Uranium Pellets
Gheorghe OLTEANU, Dragos Victor IONESCU, Adriena PARASCHIV, Mihaela Roxana
ROMAN RATEN - Institute for Nuclear Research, Romania
Theoretical estimation of minimum detectable size of PuO2 agglomerate in (Th,1%Pu)O2 fuel
K.V. Vrinda Devi a,*, K.Bijub, K.B.Khana and Arun Kumar a
aRadiometallurgy Division, bHealth Physics Division ,Bhabha Atomic Research Centre, India
Evaluation of thermal properties of Thoria-Urania fuel
Joydipta Banerjee, Santu Kaity, Koushik Bhandari, Arun Kumar
Radiometallurgy Division, Bhabha Atomic Research Centre, India
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Investigations of BaF2-ThF4 system
Sumanta Mukherjee, Smruti Dash*, S.K. Mukerjee, K.L. Ramakumara
Product development Division, aRadiochemistry and Isotope Group, Bhabha Atomic
Research Centre, India
Compatibility of silicon carbide coated graphite with lead-bismuth eutectic at 900°c
Poulami Chakrabortya*, Abhijit Ghoshb, and Gautam Kumar Deyc
aFusion Reactor Materials Section, bGlass and Advanced Materials Division, cMaterials
Science Division, Bhabha Atomic Research Centre, India
Studies on thorium bearing monazite-brabantite solid solutions: an actinide storage Matrix
Deepak Rawata, Manjulata Sahub, K. Krishnanc, Smruti Dasha
aProduct Development Division, bRadioanalytical Chemistry Division, cFuel Chemistry
Division, India
Freeze drying vs Microwave drying - methods for production of sinteractive thoria Powders
D. Annie, V. Chandramouli, S. Anthonysamy
Materials Chemistry Division, Indira Gandhi Centre for Atomic Research, India
Thorium compounds processing at ipen-cnen/sp- brazil and recent research Initiatives
Paulo E. O. Lainetti
Nuclear and Energetic Research Institute - IPEN-CNEN/SP
Brazilian National Nuclear Energy Commission - CNEN
Determination of eutectic composition and heat capacities of fuel salt (LiF-ThF4-UF4) and blanket salt (LiF-ThF4) mixtures
R. Mishra*, S. Phapale, A N. Shirsat, S. Kolay, M. Basu
Chemistry Division, Bhabha Atomic Research Centre, India
Fluorination of Thorium Oxide by Ammonium Bifluoride
Abhishek Mukherjeea and Alok Awasthib*
a Fusion Reactor Materials Section, b Materials Processing Division,
Bhabha Atomic Research Centre, India
A modified fluoride reduction route for the preparation of Thorium metal
Abhishek Mukherjeea and Alok Awasthib*
a Fusion Reactor Materials Section, b Materials Processing Division,
Bhabha Atomic Research Centre, India
A study on the solubility limit of Eu2O3 in ThO2-EuO1.5 Solid Solution
G. Panneerselvam, M. P. Antony, M .Joseph
Chemistry Group, Indira Gandhi Centre for Atomic Research, India
Determination of thermal expansion, thermal conductivity and melting temperature of ThO2 using classical molecular dynamics simulations
P.S. Ghosha*, A. Aryaa, B.K. Duttab, N. Kuganathanc, C. Galvinc and G.K. Deya
a Material Science Division, b Human Resource Development Division,
Bhabha Atomic Research Centre, India
c Department of Materials, Faculty of Engineering, Imperial College, U.K.
Recent development on recovery of Uranium, Thorium and rare earths from Monazite beach sand of India
Sujoy Biswasa*, V. H. Rupawatea, K. N. Hareendrana, Hemant Parasharb, S. B. Roya
aUranium Extraction Division, bReactor Operation Division, Bhabha Atomic Research
Centre, India
Parametric study of thermo-mechanical behaviour of 19-element PHWR fuel bundle having AHWR fuel material
R. M. Tripathi*, P.N. Prasad, Ashok Chauhan
Fuel Cycle Management & Safeguards, Directorate of Engineering - LWR, NPCIL, India
On hydrolysis behaviour of Uranium Fluoride and formation of hydrated oxyfluride of U(VI)
A. K. Tiwaria, A.K. Kalburgia, C Yadava, V Koochanaa, S. J. Patweb, M. Jafar,b S. N.
Acharyb, A. K. Tyagi,b, A Sanyala
aChemical Technology Division,bChemistry Division, Bhabha Atomic Research Centre, India
Fuel Fabrication and Reprocessing
Mock-up facility for AHWR fuel pin fabrication: A step towards fully automated fuel Fabrication
S. Pandaa*, Saurabh Guptaa, A. Saraswatb, Vijay Ahirec, Sanjeev Sharmaa, P.
S. Somayajulub, K. Jayarajana
aDivision of Remote Handling and Robotics, bRadio Metallurgy Division,
Bhabha Atomic Research Centre, India
cSymec Engineers (I) Pvt Ltd., India
Characterisation of ThO2-CeO2 sintered pellets fabricated by POP and CAP processes using impedance spectroscopy technique
P. Somayajulu, T. Mahata, R.K. Lenka, P.K. Patro, and K. B. Khan
Radiometallurgy Division, Powder Metallurgy Division, Bhabha Atomic Research
Centre, India
Thorium based fuel for AHWR
V.V. Vaze*, Y.K. Upreti, V. Shivakumar, V. Joemon, P.K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Experimental fuel for AHWR-Critical Facility
Y. K. Upreti*, V. V. Vaze, S. Jayashree, V. Shivakumar, V. Joemon and P. K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
(Th-U)O2 MOX fuel fabrication and dry recycling of the sintered rejects
Sudhir Mishra, KaushikGhoshal, Joydipta Banerjee, AmritPrakash,
K B Khan, Arun Kumar
Radiometallurgy Division, Bhabha Atomic Research Centre, India
Parametric study on co-precipitation of U/Th in MOX fuel of AHWR
S.K. Tiwari, Swaroopa Lakshmi. Y, Baidurjya Nath, Dr. D. S. Setty, G. Kalyana Krishnan
& Dr. N. Saibaba
Fuel Fabrication Facility project, Nuclear Fuel Complex, India
Study on removal of Thorium from effluent by electrocoagulation
Baidurjya Nath, Y. V. S. Swaroopa Lakshmi, S. K. Tiwari,Dr. D. S. Setty,
G. Kalyanakrishnan, Dr. N. Saibaba
Fuel Fabrication Facility Project, Nuclear Fuel Complex, India
Treatment of Uranium & Thorium bearing nitrate effluent
Baidurjya Natha, S.A. Khotb, D. Banerjeeb, C. Srinivasb, D.S. Settya, G. Kalyanakrishnana,
N. Saibabaa
aNuclear Fuel Complex, Hyderabad, India.
b Nuclear Recycle Group, Bhabha Atomic Research Centre, India
Numerical analysis of nuclear fuel element end cap resistance upset welding using SORPAS
T. Bhattacharya, Rahul Shukla, Dr. D.S. Setty, G. Kalyanakrishnan, N. Saibaba
Nuclear Fuel Complex, Department of Atomic Energy, India
Study of temperature profile in nuclear fuel element end cap resistance upset welding using analytical technique
T. Bhattacharya, Rahul Shukla, Somsekhar Reddy, Dr. D.S. Setty, G. Kalyanakrishnan,
N. Saibaba
Nuclear Fuel Complex, Department of Atomic Energy, India
Decreasing the sintering temperature of ThO2 fuel pellets using nanocrystalline toria Powder
N. Mohsenia*, S. J. Ahmadia, M. Taghizadeha, M. Roshanzamirb , M. Najafia ,S. Janitabara
aNuclear Fuel Cycle Research School, Nuclear Science & Technology Research
Institute, Tehran, Iran
bShahid Beheshti University, Tehran, Iran
A comparison of sinterabilities of thoria prepared by gel-combustion and precipitation synthesis
S. Balakrishnan and K. Ananthasivan
Chemistry Group, Indira Gandhi Centre for Atomic Research, India
Electrolytic reduction of Uranium Oxide in molten fluoride baths
Nagaraj Alangi, Jaya Mukherjee, Anupama P, K Dasgupta
Laser and Plasma Technology Division, Beam Technology Development Group,
Bhabha Atomic Research Centre, India
Study of Condensation and Flow of Liquid Metal for Laser based Purification Processes
Jaya Mukherjee, S. Sethi, Anupama P, S.P. Dey, Nagaraj A, D.R. Das, Dileep Kumar V,
M.K. Verma, K. Karmakar, Tripti A. Barnwal, S.P. Yadav
Laser & Plasma Technology Division, Beam Technology development Group, Bhabha
Atomic Research Centre, India
Irradiation behaviour of thorium based fuels
Prerna Mishra, V.P. Jathar, H.N. Singh, P.M. Satheesh, R.S. Shriwastaw, K.M. Pandit,
B.N. Rath, Priti Kotak Shah, Anil Bhandekar, G.K. Mallik, Sunil Kumar, J.S. Dubey,
J.L. Singh
Post Irradiation Examination Division, Bhabha Atomic Research Centre, India
Indian Experience on Reprocessing of Irradiated thoria
P.S. Dhami, J.S. Yadav and P.M.Gandhi
Fuel Reprocessing Division, Nuclear Recycle Group, Bhabha Atomic Research Centre, India
Development of Reprocessing Flow-Sheet for AHWR Spent Fuel
S. Panjaa, P. Jagasiab, P.S. Dhamia P.M. Gandhia
aFuel Reprocessing Division, bProcess Development Division, Bhabha Atomic Research
Centre, India
Post Irradiation Examination of thoria Based Mixed Oxide Fuel in Indian Hot Cells
J. L. Singh, P. Mishra, J. S. Dubey, H. N. Singh, V. D. Alur, P. B. Kondejkar, P.K. Shah,
V. P. Jathar, A. Bhandekar, K.M. Pandit, R. S. Shriwastaw, P.M. Satheesh, N. Kumawat,
G. K. Mallik, and S. Anantharaman
Post Irradiation Examination Division, Nuclear Fuels Group, Bhabha Atomic Research
Centre, India
Production of Uranous Nitrate with Hydrazine Nitrate as Reducing Agent in Presence of Adams Catalyst for Uranium Reconversion Purposes
K.S. Rao, K Kumaraguru and P.M. Gandhi
Fuel Reprocessing Division, Bhabha Atomic Research Centre, India
Sorption of 231Pa on Silica and the Effect of Humic Acid
Madhusudan Ghosh and Rakesh Verma
Analytical Chemistry Division, Bhabha Atomic Research Centre, India
Advanced Reactors
Conceptual design of loop-in-tank type Indian Molten Salt Breeder Reactor concept
Abhishek Basak,*, I.V. Dulera, and P.K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Study on design of Thorium based fuel pebble for IHTR-20MWTh
Indrajeet Singh, Anurag Gupta and P.D. Krishnani
Reactor Physics Design Division, Bhabha Atomic Research Centre, India
Innovative once-through thorium fuel cycle for the PTVM LWR concept
Reuven Rachamin, Emil Fridman, Alexander Galperin
Institute of Resource Ecology, Germany
Department of Nuclear Engineering, Ben-Gurion University of the Negev, Israel
Stable Salt Reactor design concept
Ian R. Scott, Tim Abram, Olga Negri
Moltex Energy LLP, Manchester University
Molten Salt Breeder Reactor Analysis on the Searching Equilibrium Composition
using Two-Cell Method
Y. Jeong, J Park and D. Lee
Ulsan National Institute of Science and Technology, Republic of Korea
Preliminary Physics Design of Accelerator-Driven thorium Cycle Fast Breeder Reactor
K.P Singh, A.K Singh and S.B Degweker
Mathematical Physics & Reactor Theory Section, Bhabha Atomic Research Centre, India
Gaseous and Volatile Fission Product Release from Molten Salt Nuclear Fuel
Ian R. Scott
Manchester University, Moltex Energy LLP
Conceptual Design of a Pool Type Molten Salt Breeder Reactor
A. Borgohain1*, A.K. Srivstava2, A.K. Srivstava1 A. Gupta2, N.K.
Maheshwari1, P.D. Krishnani2, P.K. Vijayan3
1Reactor Engineering Division, 2Reactor Physics Design Division, 3Reactor Design and
Development Group, Bhabha Atomic Research Centre, India
Thorium-based fuel utilization analysis in Fluoride salt-cooled High-temperature
Reactor
Jianlong Han, Xiangzhou Cai, Hongjie Xu*HaiBo Tan, Xiaoxiao Li, Jianhui Wu, Jingen
Chen, Shanghai Institute of Applied Physics, China
Design Review and HAZOP Studies for Stable Salt Reactor
Jon Brooking, Atkins Ltd, United Kingdom
Irradiation of Thorium Based Fuels at Research Reactors of Trombay
Kunal Chakrabarty*, Rakesh Ranjan, R.C Sharma
Reactor Group, Bhabha Atomic Research Centre, India
Technology Assessment of Near-Term Open-Cycle Thorium Energy Systems
William J. Nuttall
The Open University, UK
Use of radiotherapy LINAC for photon driven MSR (PD-MSR)
Eduardo D. Greaves, Felix Pino, Haydn Barros and Laszlo Sajo-Bohus
Universidad Simon Bolivar, Venezuela
Corrosion Aspects of Compatible Alloys in Molten Salt (FLINAK) Medium for Indian MSR Program in The Temperature Range of 550-750 °C using Electrochemical Techniques
S.J. Keny1, V.K. Gupta2, A. G. Kumbhar1, S. Rangarajan1, M. R. Daitkar2, N.K.
Maheshwari2, P.K.Vijayan2, B. N. Jagatap1
1Chemistry Group, 2Reactor Design and Development Group, Bhabha Atomic Research
Centre, India
Proposal for an Experimental Fast ADS using Th-Pu MOX fuel for Higher Actinide
Transmutation
Amar Sinha, Tushar Roy*, Y. S. Kashyap, N. K. Ray, S. Bajpai, M. Shukla,T. Patel, P.S.
Sarkar, Neutron & X-Ray Physics Division, Bhabha Atomic Research Centre, India
Experimental Studies on Heat Transfer and Pressure Drop in Pebble Bed Facility
A.K. Srivastava*, A. Borgohain, N.K. Maheshwari and P.K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre India
Experimental Studies on Natural Circulation in Molten Salt Loops
A.K. Srivastava*, A. Borgohain, N.K. Maheshwari and P.K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Natural circulation studies in lead bismuth eutectic loops
A. Borgohain, A. K Srivastava, S. S. Jana, N. K. Maheshwari and P. K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Molten salt reactor related research in Switzerland
Jiri Krepel*, Boris Hombourger, Carlo Fiorina, Sergii Nichenko, Jarmo Kalilainen,
Arnoldo Badillo, Konstantin Mikityuk, Terttaliisa Lind, Peter Burgherr, Marco Streit,
Urs Berner, DmitriiKulik, Bojan Niceno, Andreas Pautz, Horst-Michael Prasser, Martin
A. Zimmermann
Department of Nuclear Energy and Safety, Paul Scherrer Institute, Switzerland
Irradiation of Fuel Salts in the High Flux Reactor Petten
O. Benes, P. Soucek, R.J.M. Konings (JRC-ITU, Germany)
P.R. Hania, D.A. Boomstra, A.J. de Koning, I. Bobeldijk, S. de Groot, L. Pool (NRG,
The Netherlands)
Book on Molten salt reactors
Nuclear, Plasma, and Radiological Engineering Department, University of Illinois, USA
Thermal Hydraulics
Design and development of high temperature heat pipes and thermosiphons for
passive heat removal from Compact High Temperature Reactor
K.K. Panda*, A. Basak, I.V. Dulera, and P.K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Study of super-critical carbon dioxide based Brayton cycle for Indian High
Temperature Reactors
Ankur Kaushik*, S.K. Raza, I.V. Dulera and P.K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Thermal & safety analysis of Compact High Temperature Reactor (CHTR)
Syed Kazim Raza*, A. Kaushik, P.P. Kelkar, I.V. Dulera, Dr. P.K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Linear stability analysis of Thorium fueled AHWR
Rakesh Kumar, Vivek Kale, Obaidurrahman K. and Avinash. J. Gaikwad
Nuclear Safety Analysis Division, Atomic Energy Regulatory Board, India
Development and validation of a fuel performance analysis code “FRAVIZ”
Aaditya V. Majaleea* and S. Chaturvedia
aComputational Analysis Division (CAD), Bhabha Atomic Research Centre Facilities, India
<
On dryout heat flux in Porous Debris Bed
B. Ghosh and B.K. Dutta
Reactor Safety Division, Bhabha Atomic Research Centre, India
Computation fluid dynamic modelling of natural convection heat flow in unpumped
molten salt fuel tubes
Simon Leefe, Simon Carless, Ian Scott
(Moltex Energy LLP), (Wilde Analysis Ltd)
Design Feasibility Study on Corium Stabilisation in Bottom End-fitting for AHWR
Under Accident Condition
Onkar Gokhale, D. Mukhopadhyay, B. Chatterjee and R. K. Singh
Reactor Safety Division, Bhabha Atomic Research Centre, India
Uncertainty in Source Term Assessment Analysis for Thorium Fuelled Reactor under
Postulated Accident
Mahender Singh, Mithilesh Kumar, Vishnu Verma, D. Mukhopadhyay, B. Chatterjee
and R. K. Singh
Reactor Safety Division, Bhabha Atomic Research Centre, India
Blowdown and Rewetting Characteristics for AHWR Under Postulated LOCA - An
Analytical Study
D. Mukhopadhyay, B. Chatterjee and R. K. Singh
Reactor Safety Division, Bhabha Atomic Research Centre, India
Studies on Rewetting of NPP Thoria Fuels
Anil Kumar Saxena, Limaye Sanjay Prabhakar
RRSD, Reactor Engineering Division, Bhabha Atomic Research Centre, India
Thermal-hydraulic stability analysis of a natural circulation based BWR
Naveen Kumar*, A. K. Nayak and P. K. Vijayan
Bhabha Atomic Research Centre, India
Effect of distribution of volumetric heat generation on moderator temperature Distribution
A. K. Kansal, P. Suryanarayana, N. K. Maheshwari, P. K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Performance evaluation of a thermosyphon heat transport device using CFD
Bobin.S.G.1, Kapil Bodkha2*, A. Borgohain2, D.S. Pilkhwal2, Arunachala.U.C.1 and
P.K. Vijayan2
1Manipal Institute of Technology, Manipal University, India
2Reactor Engineering Division, Bhabha Atomic Research Centre, India
Heat transfer capability of thermosyphon heat transport device with experimental and CFD study
B.M. Lingade1*, Elizabeth Raju2, A Borgohain1, N.K. Maheshwari1, P.K. Vijayan1
1Reactor Engineering Division, Bhabha Atomic Research Centre, India
2Manipal Institute of Technology, Manipal University, India
Steady State and Transient CFD analysis of Compact High Temperature Reactor
B. M. Lingade*, A.M. Vaidya, A. Borgohain and N. K. Maheshwari
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Hydrodynamics of AHWR Gravity Driven Water Pool under Simulated LOCA
Conditions
I. Thangamani1, Seik Mansoor Ali2, Vishnu Verma1, V. Balasubramaniyan2
1Reactor Safety Division, Bhabha Atomic Research Centre, India
2Safety Research Institute, Atomic Energy Regulatory Board, India
Thermal and stability margin evaluation for a Thorium based BWR
Naveen Kumar*, D. K. Chandraker, A. K. Nayak and P. K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Transient following partial loss of feed water for Thorium based natural circulation Reactor
A. D. Contractor*, A. Srivastava, Rajesh Kumar and B. Chatterjee
Reactor Safety Division, Bhabha Atomic Research Centre, India
Intercode comparison of SBO scenario for AHWR
A. Srivastava*, Rajesh Kumar, B. Chatterjee, P. K. Vijayan
Reactor Design & Development Group, Bhabha Atomic Research Centre, India
A study on premature occurrence of Critical Heat Flux
K. Vishnoi*, D. K. Chandraker, P.P. Kulkarni, A. K. Nayak and P. K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Thermal Hydraulics II and Instrumentation and Control
Experimental studies on In-bundle ECCS injection for Advanced Heavy Water
Reactor
Arnab Dasgupta, D.K. Chandraker, A.K. Nayak, P.K. Vijayan
Reactor Engineering Division
Bhabha Atomic Research Centre, India
Estimation of large early release frequency for Advanced Heavy Water Reactor
T. V. Santhosh*, I. Thangamani, A. Shrivastava, Gopika Vinod, Vishnu Verma and P. K.
Vijayan
Reactor Safety Division, Bhabha Atomic Research Centre, India
Experimental and numerical investigations on thermal stratification in a large pool of water with immersed isolation condenser
Sunil Kumar1, H. Yadav3, P. K. Vijayan1,2*, A. Agrawal3, A.K. Nayak1,2* and U. Kannan1,4
1Department of Engineering Sciences, Homi Bhabha National Institute, India
2*Reactor Engineering Division, 4Reactor Physics Design Division Bhabha Atomic Research Centre, India, 3Department of Mechanical Engineering, Indian Institute of Technology Bombay, India
Chemical equilibrium analysis of dry hydrogen combustion
Aditya Karanama*, Pavan K. Sharmab, Sunil Ganjub
aK.S. Krishnan Research Associate, Reactor Safety Division Bhabha Atomic Research Centre, India
Acceptance criterion for hydrogen management in nuclear reactor containment
Aditya Karanama*, Pavan K. Sharmab, Sunil Ganjub
aK.S. Krishnan Research Associate, Reactor Safety Division, Bhabha Atomic Research Centre, India
Combined Fire Confinement and Fire influence Framework for Fire Hazard Analysis/Design Safety Margin Evaluation/Audit for Nuclear Power Plant and Reprocessing Facilities
Pavan K. Sharma
Reactor Safety Division, Bhabha Atomic Research Centre, India
Modeling of Steam Condensation using Inverse Heat Transfer Technique
Sachin Kumar Singha, Mahesh Kr. Yadava, Sameer Khandekara, and Pavan K. Sharmab*
a Department of Mechanical Engg., Indian Institute of Technology, India
b Reactor Safety Division, Bhabha Atomic Research Centre, India"
Experimental validation of an inverse heat conduction based non-intrusive thermal Sensor
Mahesh Kr Yadav1, Sachin K. Singh1, Sameer Khandekar1, Pavan K. Sharma2
1 Department of Mechanical Engineering, Indian Institute of Technology, India
2 Reactor Safety Division, Bhabha Atomic Research Centre, India
Fire Testing and Study of Liquid Pool Fire in Multiple Compartments
Pavan K. Sharma, AbhijitKushari*
Reactor Safety Division, Bhabha Atomic Research Centre, India
Indian Institute of Technology Kanpur, India"
CFD analysis of molten fluoride salt natural circulation in a rectangular loop
R. Chouhan, A. Borgohain, A.K. Shrivastav, N.K. Maheshwari and P.K. Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Design and development of self-powered sensors on wireless sensor network for standalone plant critical data management during SBO and beyond design basis events
J Aparna*, I V Dulera, P K Vijayan
Reactor Engineering Division, Bhabha Atomic Research Centre, India
Online fuel failure detection and damage severity analysis for Thorium based AHWR fuel matrix - An empirical analysis
Rajalakshmi.R, Roshini robin, Umashankari.K, Sharma B.S.V.G, Vijayan P.K.
Reactor Design & Development Group, Bhabha Atomic Research Centre, India
Experimental investigation of passive auto depressurization system (PADS) for AHWR
Mainak B.a, M. K. Sapraa*, S. Kundua, A.D.Contractorb, A. Srivastavab, P.K.Vijayana
aReactor Engineering Division, bReactor Safety Division ,Bhabha Atomic Research Centre, India
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