potential nuclear data needs

1P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007

Nuclear data for fusion applicationsan experimentalist's view

Peter Rullhusen

[email protected]


potential nuclear data needs

ITER:– diagnostics– activation (FW, BM, Div, vac. vessel, bio shielding)

IFMIF:– d-induced reactions– n-induced reactions up to 60 MeV

• shielding• radiation dammage

DEMO:– ch.p. induced reactions (d, t, 3He, ... )– n-induced reactions up to 20 MeV


diagnostics:

for example:

work carried out at IRMM in collab. with JET

activation measurements spectroscopy, partly in underground laboratory HADES

the following slides have been borrowed from a presentation at IRMM by

G. BonheurePlasma Physics Laboratory

Brussels, Belgium


ITER: Many engineering challenges

MAST JET ITER . Major radius (m) 0.9 3 6.1Aspect ratio 1.3 2.5 3.0Plasma current (MA) 1.4 4.8 15Toroidal field (T) 0.5 3.5 5.3Fusion power (MW) -- (16) 500Pulse length (s) ~2 ~10 >1000Q <<1 ~1 >10 .

Blanket moduleDivertor module

Change of extent of fusion research. Many new problems to solve.Millions of parts with very complex interfacesExtremely high heat fluxes in first wall components, & materials under neutron irradiationUnprecedented size of the super-conducting magnet and structures

presentation G.Bonheure 28/09/2007 at IRMM


Access: ITER diagnostics are port-based where possible

Each diagnostic port-plug contains an integrated instrumentation package



Neutron diagnostic systems: 4 types of systems

Time-resolved total emission(non-collimated flux)

Time-integrated emission(fluence)

2D-cameras (collimated flux along camera viewing lines)

Spectrometers (collimated flux along radial and tangential viewing lines)

Fusion power

Absolute emissionCalibration of time-resolved emission

Spatial distribution of emissiontomography

Plasma temperature and velocityPlasma density

Combination of these measurements characterizes the plasma as a neutron source



1. Time-resolved neutron emission

Fission counters:– 238U and 235U counters embedded in moderator and led shield– Operate both in counting and current mode– Dynamic range: excellent (10 orders of magnitude)– 3 pairs installed at different positions around JET– Low sensitivity to X and radiation– No discrimination between 2.5 and 14 MeV neutron emission– Calibrated originally in situ with californium 252Cf neutron source,

periodically recalibrated using activation technique



2. Time-integrated neutron emission

Neutron activation method

Sample activity measurements:Sample activity measurements: 1) gamma spectroscopy measurements >>> most widely used reactions at JET: DD neutrons - 115In(n,n’)115mIn, DT neutrons - 28Si (n,p)28AL, 63Cu(n,2n)62Cu, 56Fe(n,p)56Mn >>> detectors : 3 NaI, HPGe (absolutely calibrated)2) delayed neutron counting (235U,238U,232Th) >>>detectors: 2 stations with six 3He counters

Calibration: accuracy of the time-resolved measurements is typically ~ 8-10% for both DD and DT neutrons (7% at best using delayed neutron method) – after several years of work !!

Samples used as flux monitors are automatically transferred to 88 Irradiation ends



Confined fast ions and fusion productsLosses of fast ions and fusion products

Other fusion products measurements

d + d p (3024 keV) + t (1008 keV)

d + 3He p (14681 keV) + (3670 keV)

d + d n (2450 keV) + 3He (817 keV)

d + t n (14069 keV) + (3517 keV)

+ ICRF accelerated ions



NaI(Tl)

BGO

BGOHow to measure confined ions with gammas?

Detection of -ray lines due

to nuclear reactions with fuel

and with the main plasma

impurities, Be and C

protonsD(p,)3HeT(p,)4He9Be(p,)10B9Be(p,p’)9Be9Be(p, )6Li12C(p,p’)12C

Fast scintillatorsLaBr3 :Ce (known as BrilLanCe):

•Light yield 60,000 photons/MeV•Energy resolution - better than 3% •Decay times - < 20 ns (NaI: 250 ns)

LYSO:•Decay time 40ns •Better light output ( 32,000 photons/MeV ) •Slightly radioactive ( - and - radiation)



Activation probe

• SAMPLES activation by charged particles • ANGULAR DISTRIBUTION (v magnetic field)

of radionuclides :

anisotropic for charged particles • Absolute measurements of time-integrated

losses of charged particles• Recent results from D – 3He plasmas• 10B (p,α) 7Be , 7Li (p, n) 7Be• Detection of 14.6 MeV protons from threshold

reaction

• 48Ti(p,n)48V Eth : 5 MeV



diagnostics (cont.)

work carried out at IRMM in collab. with JET:activation of Ti, MgF2 and TiVAl alloy ( spectr. partly in underground lab)

J. Gasparro et al., Appl. Rad. Isot. 64(2006) , G. Bonheure et al., Phys. Scr. 75 (2007) 769


diagnostics (cont.)

activation of Ti, LiF, B4C and W ( spectr. partly in underground lab)

E. Wieslander et al., to be publ.


ITER

activation, rad. damage.

Example: materials under consid. for Blanket ModuleBeAlCuCrZrTiSSinconel


structural materials

D. L. Smith, Neutron Reaction Data for IFMIF: example Fe


Summary: what IRMM can contribute

n-induced reactions:– VdG: En ~ 1 MeV – 25 MeV– ch.p. induced reactions (p,d,): up to 7 MeV

(t,x) look for inverse reactions– activation: half-lives > 10 min (external); very long: HADES

~ 10 s – 1 s (beam chopper 1 Hz – 5 kHz)

– high-resolution TOF: total, capture, (n,n') , (n,2n)with installation of new ECR source (end 2007):

– optimised for H, D, He+ and He++ at i>60 A – possibility of accelerating 3He, 6Li (to be investigated)

proposed: 200 A, 2 MV singletron for high-intensity measurements at low energies


what IRMM can do (cont.)

example: recent activ. meas. on W isotopesV. Semkova, A. Plompen

12 14 16 18 20

5

10

15

ENDF/B-VII JEFF-3.1 JENDL-3.3 EMPIRE EAF-2007

This work (enriched) This work (natural) 2003 Filatenkov 1997 Kong Xiangzhong 1993 Grallert 1959 Lindner

182W(n,p)182Ta

Neutron energy (MeV)

Cro

ss s

ectio

n (m

b)

12 14 16 18 200

5

10

This work 2003 Filatenkov 1999 Filatenkov 1997 K. Xiangzhong 1993 Grallert 1992 Kasugai 1988 Ikeda 1975 Qaim 1959 Coleman

TALYS-0.68 EAF-2007 JEFF-3.1 JENDL-3.3 EMPIRE ENDF/B-VII

184W(n,p)184Ta

12 14 16 18 20

1

10

This work (enriched) This work (natural) 2003 Filatenkov 1993 Grallert 1975 Qaim 1959 Lindner

EAF-2007 ENDF/B-VII EMPIRE JEFF-3.1 JENDL-3.3

183W(n,p)183Ta

12 14 16 18 20 22

1

10

EMPIRE JEFF-3.1 JENDL-3.3 TALYS-0.68 EAF-2007 ENDF/B-VII

This work 2006 Avrigeanu 1999 Filatenkov 1995 Murahara 1994 Satoh 1992 Kasugai 1975 Qaim

186W(n,p)186Ta

182W(n,p)182Ta, 183W(n,x)182Ta

183W(n,p)183Ta, 184W(n,x)183Ta, 183W(n,n')183mW

184W(n,)181Hf, 184W(n,p)184Ta, 184W(n,2n)183mW

186W(n,)183Hf, 186W(n,x)185Ta, 186W(n,p)186Ta, 186W(n,2n)185mW



example: upcoming capture and transmission meas. on W isotopesNUDAME proposal:



FNG expt. for FENDL validation (contr. P. Batistoni):

Si, Nb, Ni, Fe, Sr, Al: which reactions? which enenergy range?

Be/Li2CO3 breeder:9Be(n,n) n angular distribution:

new set-up for elast. scatt.9Be(n,2n) only cross sections

remark: NRG (A. Hogenbirk) presented at NEMEA-4 workshop a method to carry out uncertainty calculations in arbitrary 3D geometries using MCNP as a radiation transport code.

potential nuclear data needs

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