Transcript Slide 1

BgNS Conference 2014
Reactor Dosimetry News and
Prospects
Mladen Mitev
International Symposium on
Reactor Dosimetry
Organized every three years by
The European Working Group
on Reactor Dosimetry
Europe, Africa, Asia (other),
and Australia
ASTM International Committee E10
on Nuclear Technology and Applications
Americas, East and Southeast Asia, Israel
ISRD 15
Held in Aix-en-Provence,
18-23 May, 2014
Scientific program included following topics:
• Reactor surveillance and plant life management
• Nuclear data
• Neutron and gamma transport calculations and modelling
• Experimental techniques
• Benchmarks and intercomparisons
• Dosimetry for research reactors : MTR, ZPR, ADS, fusion...
• More than 150 participants from 30 countries
• 6 Workshops on Tuesday 20th and Thursday 22nd
• 2 poster sessions on Monday 19th and Wednesday 21st
Reactor Surveillance and Plant Life
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In-vessel and ex-vessel
dosimetry programs
AGR dosimetry experience
Fluence-to-dpa corelation
attempts
Core to vessel benchmark
experiments
CEA/ Cadarache FLUOLE
Benchmark
Ex-vessel neutron Dosimetry System for CE-design KSNP Plants
Nuclear data
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Validation of the recently
released International Reactor
Dosimetry and Fusion File
(IRDFF) in different fields
Evaluation of the 93Nb
Reaction Cross-Section
Analysis of induced gamma
activation by D-T neutrons in
selected fusion reactor
relevant materials with EAF2010 and IRDFF-1.0
Dosimetry for research reactors
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Older dosimetry data
reviewing and documenting
Contribution of accelerator
facilities to the reactor
dosimetry
Extensive dosimetry demand
of BNCT recognized
Advances in radiation
heating measurements using
calorimeters
Dosimetry for research reactors
Two main fields of calorimeters application:
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Electronics
Fusion technology like energy deposition in
blanket, magnetic coil insulation, etc.
Neutron and gamma transport
calculations and modelling
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Focussed on methods coupling, implementation
of core techniques
GEN 4 problems modelling:
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RPV damage
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Dose evaluations
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Tritium production
Neutron and gamma transport
calculations and modelling
The Consortium for the Advanced Simulation of
Light Water Reactors
Lead by Oak Ridge National Lab and funded by U.S.
Department of Energy, with participation from
laboratory, academic, and industry partners
Established in July 2010 for the purpose of providing
advanced modeling and simulation solutions for
commercial nuclear reactors.
Primary goal is to provide coupled, higher-fidelity,
usable modeling and simulation capabilities, needed
to address light water reactor (LWR) operational and
safety performance-defining phenomena that are not
yet able to be fully modeled taking a first-principles
approach.
TITAN as main computing power (almost 300 000
cores and almost 19 000 GPU accelerators) and F-5Figure 1. A User Interacting with a 3D Neutron Flux Distribution in the F-5 Storm System at ORNL
Storm as interface system (Joel A. Kulesza, et. al.)
Thank you!