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NEUTRON DATA

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Title: NEUTRON DATA


1
NEUTRON DATA
  • A CHALLENGE FOR SUSTAINABLE, CLEAN ENERGY
  • C.Borcea

2
OUTLOOK
  • INTRODUCTION
  • NEUTRON DATA (ND) WHY AND HOW
  • ND AT IRMM NP
  • CONCLUSION

3
INTRODUCTION
  • RECENT HOT LINES IN THE NEWS
  • -CHERNOBYL
  • -PRICE OF CRUDE
  • IMPLICATIONS
  • MAKE NUCLEAR ENERGY SAFE AND CLEAN BY
  • -NEW GENERATION OF REACTORS
  • -WASTE PROCESSING

4
NEUTRON DATA WHAT IS THAT?
  • DATA CONCERNING THE CROSS SECTIONS OF NEUTRON
    INDUCED REACTIONS ON VARIOUS MATERIALS
  • The neutron can
  • -scatter elastically
  • -scatter in-elastically (followed by ?
    emission)
  • -be captured (followed by gamma end/or
    particle
  • emission)
  • -induce fission
  • -induce a (n,xn) or a (n,cp) reaction

5
(No Transcript)
6
NEUTRON DATA WHAT FOR?
  • REACTORS OF A NEW GENERATION AND/OR ADS
  • RADIOACTIVE WASTE PROCESSING
  • FUSION REACTORS (ITER)
  • SAFETY AND SAFEGUARDS
  • MEDICINE, FORENSICS
  • ELEMENT TRACING, etc.

7
NUCLEAR ENERGY KEY ISSUES
  • SAFETY (keff)
  • SUSTAINABLE (BU, CLOSED CYCLE)
  • WASTE (PT)
  • NONPROLIFERATION

8
NEW GENERATION REACTORS HOW?
  • DESIGN OF INOVATIVE NEW REACTOR TYPES IS DONE
    ESSENTIALLY BY USING
  • -PERFORMANT, STATE OF THE ART CODES FOR MONTE
    CARLO SIMULATION and
  • -RELIABLE CROSS SECTION LIBRARIES WITH INFO
    CONCERNING THE DATA PRECISSION
  • -BENCHMARKING

9
WASTE PROCESSING PT
  • Radiotoxicity of Nuclear Waste
  • production of Pu and "minor actinides" (Np,
    Am,...) by "breeding" (combination of neutron
    capture and beta decay)
  • production of long-lived radioactive fission
    products

Partitioning separate and recycle U,
Pu Transmutation "burn" minor actinides (by
neutron-induced fission), "transform" long-lived
fission products into short-lived or
stable isotopes (by neutron capture) requires
fast neutrons
10
LIBRARIES WHAT IS THE PRESENT STATUS?
  • MANY LIBRARIES, GENERALLY CONCORDANT BUT
  • ZONES WHERE DATA ARE ABSENT OR LARGE (20 or
    more) UNCERTAINTIES (especially for structural
    materials but also for MA)
  • REGIONS WHERE DATA ARE DISCREPANT
  • CROSS SECTIONS EXIST BUT DATA PRECISSION AND
    CROSS INFLUENCE OF DIFFERENT FACTORS (SO CALLED
    COVARANCE MARIX) INSUFFICIENTLY KNOWN OR NOT
    KNOWN AT ALL

11
ILLUSTRATION
Example 1 large uncertainties in data files due
to lack of experimental data
extrapolations based on previous knowledge
IRMM
previous knowledge
12
ILLUSTRATION
Example 2 large uncertainties in data files due
to inaccurate experimental data
61Ni(n,p)61Co
predictions from model codes
13
NEUTRON DATA HOW?
  • A NEUTRON SOURCE IS MANDATORY
  • THERE IS NOT AN ALL PURPOSE NEUTRON SOURCE
  • SUCH FACILITIES ARE HIGH-TECH INSTALLATIONS
    USSUALLY WITH TRANS-NATIONAL ACCESS

14
ILUSTRATION NEURON FACILITIES IN THE WORLD
  • LOS ALAMOS
  • OAK RIDGE
  • JAPAN
  • RUSSIA
  • n_TOF (CERN)
  • GELINA (IRMM)
  • VdG accelerators (France, Germany, Belgium, etc.)
  • HIGH-FLUX REACTORS
  • FUTURE SPIRAL2?

15
NEUTRON DATA FOCUS ON GELINA
  • IRMM A TRADITION IN QUALITY NUCLEAR DATA
  • FACILITY, CHARACTERISTICS
  • CAPTURE CROSS SECTIONS
  • TRANSMISSION CROSS SECTIONS
  • FISSION CROSS SECTIONS
  • INELASTIC AND (n,2n) CROSS SECTIONS

16
Reference Laboratory for Neutron Physics
  • Provide European safety authorities and
    industry with neutron data needed for
  • the feasibility study of waste transmutation
    facilities and advanced systems
  • the safety assessment of nuclear installations
    and the nuclear fuel cycle

7 MV VdG
150 MeV Electron Linac
High-resolution neutron cross-section
data measurements
Facilities GELINA and VdG exclusively used for
neutron production
17
Geel Electron Linear Accelerator GELINA
Continuous energy spectrum, Time-of-flight
measurements
n
L
e- 150 MeV
U
18
GELINA a powerful neutron source
High-energy electron accelerator
Electron-neutron conversion target
  • 150 MeV electron accelerator (10 ns, 10 A)
  • pulse compression to 1 ns and 100 A
  • 800 bursts / s
  • uranium target - mercury cooled
  • 4 1010 neutrons / burst

19
CERN TOF Facility spallation neutron source 24
GeV protons, 31013 p/pulse ?t 10 ns,
frequency 0.4 Hz Pb target 40 cm x 40 cm diam.
water moderator Neutron
production rate 21016 n/pulse 1016
n/s forward directed fixed flight path L
200 m 7106 n/cm2 per pulse (2.4
s) single user facility, En lt 109 eV very high
n flux per pulse radioactive targets, rare
isotopes
GELINA electrons ? bremsstrahlung ? neutrons
0.15 GeV electrons, 7.51011 e- /pulse
?t 1 ns, frequency 800 Hz U target torus,
3 cm x 30 cm outer diam. (
water moderator ) Neutron production rate
41010 n/pulse 31013 n/s isotropic several
stations with L 10 m - 400 m 3103 - 2 n/cm2
per pulse (1.2 ms) multi-user facility, En
lt 10 MeV very high energy resolution, flux
1/3 of TOF in resonance region
20
Van de Graaff accelerator monochromatic neutrons
via nuclear reactions
e.g.
21
radiotoxic inventory
Typical radiotoxic inventory as a function of
time in Sv per metric ton of heavy metal
fission products
22
radiotoxic inventory
contribution from long-lived fission products
23
Nuclear Waste Transmutation
Example long-lived fission product 129I via
neutron capture 129I (1.6 107 a) n ? 130I
(12.4 h) ? 130Xe (stable)
feasibility studies capture and transmission
experiments at GELINA (collab. with CEA)
?
n
129I
? -
130I
1.6 107 a
130Xe
12.4 h
stable
24
High Resolution Measurements on 99 Tc at GELINA
25
206Pb(n,g) res. shape analysis
Experiments at GELINA
304 resonances observed (221 in evaluated
files) E0, g?? up to 620 keV (before up to 200
keV ) g?n up to 80 keV
A. Borella, P. Schillebeeckx
26
Inelastic scattering mechanism by which fast
neutrons lose energy energy spectrum in
accelerator driven systems (ADS) structural
materials (Al,Fe) criticality coolant
materials (Na,Pb) coolant void effect
27
27Al Inelastic Neutron Scattering
Eg1.0145 MeV
Eg0.8438 MeV
28
58Ni, Inelastic cross section
L. Olah, DNE, HU C. Borcea, SV, RO L.C.
Mihailescu, GH,RO IReS Strasbourg U. and TU
Vienna U. Belgrade nTOF collaboration
29
207Pb(n,ng) and (n,2ng) measurements
Mihailescu et al. Rudolf et al.
200 m FP, Gelina fast flux 8 ns FWHM TOF-resol. 4
HPGE (3x 95, 1x 80 )
Continuous energy up to 20 MeV High resolution at
low energy
30
207Pb(n,ng)
31
209Bi(n,ng), Deduced total inelastic
32
ROMANIA AND IRMM-NP UNIT
  • VISITING SCIENTISTS (2 SENIOR RESEARCHERS FROM
    NIPNE-BUCHAREST AND 2 PROFESSORS FROM BUCHAREST
    UNIVERSITY)
  • DNE (2 SENIOR RESEARCHERS FROM NIPNE-BUCHAREST)
  • ONE PHD THESIS DONE IN IRMM (GRANT HOLDER)
  • 4 POST-DOCTORAL FELLOWS (NIPNE-BUCHAREST)
  • NEURON MEASUREMENTS, EVALUATIONS AND
    APPLICATIONS NEMEA-2 WORKSHOP ORGANIZED BY IRMM
    AND NIPNE AT BUCHAREST (2004)

33
CONCLUSION
  • HIGH QUALITY NEUTRON DATA ARE NECESSARY
  • COMPLEMENTARITY AND COOPERATION
  • MEASUREMENT-EVALUATION CYCLE
  • ATRACT NEW INSTITUTIONS/PEOPLE
  • COMMUNICATE!
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