Reactor Dosimetry News and Prospects

Mladen Mitev

BgNS Conference 2014

International Symposium on Reactor Dosimetry

Organized every three years by

The European Working Groupon Reactor DosimetryEurope, Africa, Asia (other),and Australia

ASTM International Committee E10on Nuclear Technology and ApplicationsAmericas, 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

In-vessel and ex-vessel dosimetry programs

AGR dosimetry experience Fluence-to-dpa corelation

attempts Core to vessel benchmark

experiments

CEA/ Cadarache FLUOLE Benchmark

E x -v esse l n eu tro n D o sim etry S yste m fo r C E -d esig n K S N P P lan ts

Nuclear data

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 EAF-2010 and IRDFF-1.0

Dosimetry for research reactors

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: Electronics Fusion technology like energy deposition in

blanket, magnetic coil insulation, etc.

Neutron and gamma transport calculations and modelling

Focussed on methods coupling, implementation of core techniques

GEN 4 problems modelling: RPV damage Dose evaluations Tritium production

Neutron and gamma transport calculations and modelling

The Consortium for the Advanced Simulation of Light Water ReactorsLead 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-5 Storm as interface system (Joel A. Kulesza, et. al.)

F ig u re 1 . A U se r In te rac tin g w ith a 3 D N eu tro n F lu x D is tr ib u tio n in th e F -5 S to rm S yste m a t O R N L

Thank you!