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Speaker List

Displaying 18 speakers out of 18
ASMAE ETTOUFI (Hassan II University of Casablanca, Morocco)
NORM Industries wastes modelling with Monte Carl Gean14 Summation
ATHIRA KUMARI USHA VIJAYA RAJ (Bhabha Atomic Research Centre, India)
Defects in Pyrochlore structure for waste management
CILLIAN COCKRELL (QUEEN MARY UNIVERSITY, UK), OLIVER DICKS (QUEEN MARY UNIVERSITY, UK)
Modelling interactions of Ionising Radiation with crystalline material
DENNIS SOLOMON BALAMI (University of Maiduguri, Nigeria)
Enhancing Radioactive WASTE management through Precision Reactor Core Lifetime Estimations
DESAI RAMESH JAYANTILAL (MCF (Shreeji Medical Cyclotron Facility), India)
Simplest method to derive decay factor of radionuclide
HAIBO PENG (Lanzhou University, China)
Interactions of Ionising Radiation glass structure
JOHANN VAN ROOYEN (North West University, South Africa)
Detriment of exposure to ionising radiation — radiation risk
Introduction to radiation transport and shielding of ionising radiation
Overview of the ORIGEN and ORIGAMI codes in SCALE-6.2 and 6.3
Demonstration of the calculation of (Nuclide,Activity) (N_i;A_i (t)) inventories in radioactive waste, using the codes ORIGEN, ORIGAMI and FISPACT-II. Translating (N_i;A_i (t)) inventories to radiation emission source terms using ORIGEN and MCNP-SOURCE-APP
Demonstration of the modelling of chemical processing that feeds the production of radioactive waste, using the codes ORIGEN and FISPACT-II.
Case studies:
(1) Solid residue from irradiated target-plates for (n,f) (_^99)Mo production;
(2) LILW-SL liquid radioactive waste produced in the production of (n,f) (_^99)Mo.
From the “Age of Equations” to the “Age of Simulations”.
Introduction to the radiation transport code MCNP6.2 and the development of calculation models for simulations.
Conceptual mapping of the terms in the Boltzmann transport equation to an MCNP calculation model.
Given a (Nuclide,Activity) (N_i;A_i (t)) inventory, calculate radiation emission source terms using (1) the utility code MCNP_SOURCE_APP as well as SCALE ORIGEN
Development and execution of MCNP calculation models
Case study 1: Dose rate calculation for radioactive waste — point source
Development and execution of MCNP calculation models
Case study 2: Dose rate calculation for radioactive waste. Point source — volume sources
Development and execution of MCNP calculation models
Case study 3: Concrete drum filled with a simple radionuclide content. Calculation of required wall thickness of the concrete
Development and execution of MCNP calculation models
Case study 4: Hematite or barites concrete drum filled with cemented liquid radioactive waste from (n,f) (_^99)Mo production. Calculation of the contact dose rate and Transport Index (TI) after a selection of decay times
Calculations in support of the isotopic characterisation of irradiated nuclear fuel assemblies from research reactors and power reactors.
ORIGAMI →EXCEL→ MCNP. Examples of spent fuel dose rate and cask evaluation calculations using the above toolchain
Modelling with MCNP: Charged particle interactions with glass, cement, ceramics and graphite. Calculation of dose-depth curves for α-particles, electrons, positrons and ionising photons.
JOHN PROVIS (Paul Scherrer Institute, Switzerland)
Interactions of Ionising Radiation interactions with cement waste form or concrete container
Interactions of Ionising Radiation interactions with cement waste form or concrete container
MAIK LANG (University of Tennessee, USA)
Fundamental Waste Form Science
Introduction to irradiation effects, simulating damage profiles and quantifying radiation effects and amorphous phase fractions using SRIM/TRIM and AMORPH
Model the transport of charged ions in matter using code SRIM/TRIM
Model the transport of charged ions in matter using code SRIM/TRIM
Introduction to ESTAR, PSTAR and ASTAR as simplified versions of SRIM
Practical use of computer codes “amorph” to simulate X-ray diffraction patterns of practically amorphous materials where irradiation lead to amorphization
Practical use of computer codes “amorph” to simulate X-ray diffraction patterns of practically amorphous materials where irradiation lead to amorphization
Detriment of exposure to ionising radiation — radiation risk
MERRY GUPTA (Inter-University Accelerator Centre (IUAC), India)
Enhanced radiation resistance of nano-crystalline zirconolite
MICHAEL OJOVAN (Imperial College, UK)
Interactions of Ionising Radiation with water (radiolysis)
MICHEL J. SASSI (PNNL-USA)
The modelling of transmutation events in HLW
NICOLA SERIANI (ICTP, Italy)
Opening & welcome Presentation -Background of ICTP
Poster Awards to winners, concluding session
RITU KUMARI PILANIA (Central University of Gujarat, India)
Simulation of the radiation effects on the borosilicate glass ceramic wasteforms for high-level waste immobilization
RUMU HALDER BANERJEE (Bhabha Atomic Research Centre, India)
Irradiation effects in Phosphate based matrixes
RUMU HALDER BANERJEE (Bhabha Atomic Research Centre, India)
Irradiation effects in Phosphate based matrixes
WILLIE MEYER (IAEA, Austria)
Introduction of lecturers
Administrative guidelines
Completion of questionnaire
Presentation: why modelling ionization radiation in waste forms ?
Interactions of Ionising Radiation: Use of G value tables for modelling
Review of school/workshop
YOUMMA GHONEIM (Joint Institute for Nuclear Research, Russian Federation)
Plasma utilization for reactor waste treatment

Organizers

Willie MEYER (IAEA, Austria), Rebecca ROBBINS (IAEA, Austria), Michael OJOVAN (Imperial College, UK), Local Organiser: Nicola Seriani (ICTP)

Co-sponsors