Physics of Nuclear Energy at IN2P3 S. David CNRS/IN2P3 NuPECC IPHC Strasbourg March 14th 2014
12
Physics of Nuclear Energy at IN2 S. David CNRS/IN2P3 NuPECC IPHC Strasbourg March 14th 2014 1
description
Physics of Nuclear Energy at IN2P3 S. David CNRS/IN2P3 NuPECC IPHC Strasbourg March 14th 2014. Physics of Nuclear Energy. Interdisciplinarity. Scenarios studies. System studies. Nuclear physics. Nuclear data. Society. Nuclear models. Neutronic simulations. Targets. - PowerPoint PPT Presentation
Transcript of Physics of Nuclear Energy at IN2P3 S. David CNRS/IN2P3 NuPECC IPHC Strasbourg March 14th 2014
1
Physics of Nuclear Energy at IN2P3
S. DavidCNRS/IN2P3
NuPECCIPHC StrasbourgMarch 14th 2014
2
Nuclear physics
Nuclear data
System studies
Scenarios studies
Neutronic simulations
Experiment
Society
Interdisciplinarity
Physics of Nuclear Energy
Targets
Experiment
Evaluation
Data libraries
Radiochemistry
Nuclear models
3
Main collaborations
European programsNUDAMEEUFRATEFNUDAT ERINDANUDATRA ANDES CHANDA
FacilitiesNeutron beamsCharged particlesNuclear reators
IN2P3 teams
Nuclear data for reactors
4
1eV 10 MeV 1 GeV
Thermal reactorsFast neutron reactorsAccelerator-driven subcritical reactors
N-TOF@CERN – continuous neutron source – time of flight
Licorne@IPNO
GSI Electromagnetic fission
Neut
ron
sour
ce
Indi
rect
m
etho
ds
Differential cross-sections (fission, capture, (n,xn), (n,n’)Branching ration (fission products, beta decays, …)Integral measurements, Indirect methods, nuclear parameters (level density, …)
…
Nuclear data for reactors
GELINA (Geel) continuous – time of flightNFS@Ganil
5
238U(n,n’) libraries 238U(n,n‘) neutron inelastic scatering
Governs the slowing-down of the neutrons at high energy just after the fission
Responsible of the slowing-down below the fission threshold of non-fissile nuclei
Impacts on delayed neutrons, void coefficient, neutron balance for breeding
GRAPhEME@GELINA
A strong collaboration theory/experiment is needed to understand the discrepancy between measurement and experiment and to improve neutron libraries
Nuclear data for reactors : focus on 238U(n,n’)
6
CACAO : provides radioactive targets and target characterization
Fabrication : electroplatingR&D: ionic liquid for O-free target
252Cf and 231Pa target
Characterization :
R&D: C²ASCERA: multi-analysis chambercoupling SEM and NRA analysis
Thin backing (750 nm Al): 235,238U, 232Th target
spectrometry Thickness, cartography, homogeneityautoradiography
Atomic Force Microscopy Surface state analysis
235, 238U; = 70 mmbacking: 20µm Al
chemical and isotopical analysis
Inauguration: 2013, July 12th
Needs for radioactive
targets
Needs for well characterized
targets
7
Experimental reactor physics
7
VENUS reator (SCK Mol)Fast spectrum, Lead, U metal enriched 30%~0 power reactorCritical and subcritical mode
GENEPI-3C neutron source (IN2P3)
Develop an experimental method for the on-line measurement of the subcriticality level
8
GENEPI-3C neutron source : multiple modes for different experimental methods
Subcriticality system : a new way to make experimental reactor physics
beam
Standard method used for critical systems
Innovative method (IN2P3)
Time response to a pulsed neutron source at different locations in the core
Experimental reactor physics
9
Simulation, Systems and Scenarios
Detailed neutronic simulations
Innovative methods
Scenario studiesFissile inventories
Impacts on fuel cycleWaste production
System studiesFuel evolution
Safety parameters
Exploring mid / long term innovative strategies • innovative cycles in « standard reactors » (water, sodium)• innovative systems reactors+cycle : ADS, Molten Salt reactor
10
Simulation Systems Scenarios
From detailed neutronic simulation …. to macroscopic scenario studies
Sensitivity to nuclear dataImpacts on fuel evolution,
safety parameters, …
Impacts of breeding and transmutation on induced radiotoxicity (waste and fuel)
Fast sodium reactor / Uranium cycle
transmutation
waste
fuel
11
Accelerator driven systems
Dedicated to waste transmutationAccelerator R&D (see J.S. Bousson)Proton beam
Increasing the power of transmuterreducing the numer of reactors dedicated to waste transmutation
Molten Salt Reactor (MSFR)
Liquid fuel, fluoride, thorium cycleOn-line reprocessingDesign studies, safety studiesCoupling neutronic / thermalhydraulic
Simulation Systems Scenarios
12
Nuclear PhysicsReactor physics
Exp. / Sim.
02000400060008000
total (TWh/y)individual kWh/cap/y
What place for nuclear power in the future?Collaboration with Techno-economy , climatologists, …
Opening toInterdisciplinarity
Opening toSociety
Proliferation problematicsUse the neutrinos to measure
what happens in the core from outside
Academix teaching : nuclear energy, reactor physics, nuclear wasteExpertise for society : parlementary office, french law on nuclear waste, public debates, …
Collaborations• Other CNRS instituts, NEEDS• CEA and French nuclear industry• European programs• International collaborations
