Arjan Plompen Experiments NEA member countries
Overview JEFF KAERI summary (Cho) Nuclear data weeks GEDEPEON November 2011 ANDES April 2012 ERINDA EUFRAT Collaboration ORNL (Danon)
Summary of the GEDEPEON-JEFF workshop 28-29 November 2011
Heavy Mass and Isotopic yield measurements of 233 U(n th,f) on the Lohengrin spectrometer at ILL G. Kessedjian (CNRS Grenoble) Mass yields > Ionization chamber Isotopic yields > g spectrometry Delayed neutron > b n detector
Kessedjian, ILL experiments
Jurado, FY at GSI (Taieb et al.)
Experimental investigations on prompt fission neutrons spectra T. Granier, CEA DAM DIF, Bruyères le Châtel, Arpajon, France PFNS & n Expts: LANL, BRC Coll.: BRC, LANL, IRMM 12 days beam 1 mg 238U target
Nbr of fissions (u. a.) X. Ledoux, delayed neutrons 232 Th 1,E-04 1,E-06 Th sample Th sample + detector 1,E-08 1,E-10 0 2 4 6 8 10 Energy (MeV) F det (t) t(s)
J.-M. Laborie, G. Bélier, J. Taieb, CEA, DAM, DIF Prompt fission gammas First results in 252 Cf spontaneous fission in 238 U fast neutroninduced fission : 1.7 & 15.6 MeV Technical development goes on (BGO det. 2 ns First work since 70s!
Number of g per (fission.mev) J.-M. Laborie, G. Bélier, J. Taieb, CEA, DAM, DIF Prompt fission gammas 10 1 n(15.6 MeV)+ 238 U n(1.7 MeV)+ 238 U n th +235U (Verbinski et al.) 10 0 10-1 First results in 238 U fast neutroninduced fission : 1.7 & 15.6 MeV 0,0 0,5 1,0 1,5 2,0 2,5 3,0 3,5 4,0 g-ray energy (MeV)
Prompt fission gammas Detector development LaBr3:Ce, LaCl3:Ce, Ce:Br3 Efficiency, resolution, background 2x4fold pcvf double-e detector TOF FF-g to clean up g-spectrum 235 U(n th,f) Budapest
TAGS and Pn, Algora, IFIC-Valencia
TAGS and Pn, Jyväskylä, Penttilä A method to determine independent isotopic fission yields utilising a Penning trap has been developed Method has been applied to charged particle induced fission: p+ 238 U, p+ 232 Th, d+ 238 U New location of the IGISOL mass separator laboratory allows using intense proton to produce neutrons and use neutron induced fission to produce neutron rich nuclei, lab under reconstruction
n_tof (*) is a spallation neutron source based on 20 GeV/c protons from the PS of CERN from thermal to ~1 GeV neutron energy E. Chiaveri n_tof developments Practically all is analysed and published EXFOR: to do (T. Ware/Birmingham) Experimental area Class A new target second campaign started 2009-2012 restart 2014
Overview of the n_tof spallation target area EAR2 (@20 m from pit, above ground) ISR To be built Technical gallery (@10 m from pit) n_tof target pit Existing hole JEFF-GEDEPEON Workshop 28/29 November 2011
N_TOF fission, Colonna n_tof Phase 1 235 U, 238 U, 232 Th, 233 U, 234 U, 236 U, 237 Np, 241,243 Am, 245 Cm, 209 Bi, nat Pb n_tof Phase 2 240 Pu, 242 Pu, 232 Th, 237 Np
TRAKULA Sample prep. Detector devel. Fission XS meas. AMS, Felsenkeller Training
Normalized Response Cross-section (barn) Pillon, diamond detectors spectrometer n+c cross sections 18.48 MeV 18.96 MeV 20.54 MeV 1E-3 1E-4 1E-5 1E-6 1E-7 0.30 0.25 0.20 0.15 this paper CENDL-3.1 EAF-2007 1982,G.Dietze+ 1976,A.P.Stevens 1980,P.Dimbylow 7.33 MeV 13.79 MeV 8.3 MeV 7.83 MeV 17.99 MeV 17.48 MeV 16.93 MeV 16.3 MeV 7.5 16.5 1E-8 20.5 Neutron Energy (MeV) 0.10 0.05 0.00 6 8 10 12 14 16 18 20 22 Neutron energy (MeV) 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 Deposited Energy (MeV)
U-234(n,f) anisotropy Al-adili, Hambsch, Oberstedt, Pomp
Summary of the ANDES-JEFF workshop 23-24 April 2012
238 U(n,n g) A. Bacquias et al. CNRS-IPHC Strasbourg, JRC- IRMM, CEA/DAM BRC, IFIN-HH
Preliminary
23 Na(n,n g) Upper limit of energy 3.84 MeV Total inelastic and level inelastic Careful efficiency check gamma-ray detectors Final data delivered to CEA, NRG, BNL, JSI Report EUR 24871 EN. Group cross section < 2.5 %! C. Rouki et al., Nucl. Instrum. Meth. A 672 (2012) 82
Inelastic versus other data and evaluations Cross section (b) E n (kev)
Level cross sections Cross section (b) E n (kev)
Märten/Kopecky IRMM data 1994/1997 8 liq.scint, 8 angles. n-g discrimination n elastic, g inelastic, normalised n C(n,n)C, g 10 B(n,a) R-matrix-fit TOT Consistency check EL+INL TOT! R-matrix-fit INL
N_TOF 241 Am(n,g), Cano Ott, Gunsing et al. C 6 D 6 Preliminary TAC Preliminary JEFF-GEDEPEON Workshop 28/29 November 2011
N_TOF 238 U(n,g), preliminary Cano Ott, Ware, Gunsing et al.
IRMM 241 Am(n,g), nearly final Schillebeeckx, Kopecky, Lampoudis, Gunsing et al.
IRMM 238 U(n,g), ongoing Schillebeeckx, Kopecky, Lampoudis, Gunsing et al.
N_TOF 241 Am(n,f) N. Colonna et al.
N_TOF 243 Am(n,f) N. Colonna et al.
N_TOF 245 Cm(n,f) N. Colonna et al.
N_TOF 240,242 Pu(n,f) ongoing N. Colonna et al.
IRMM 240,242 Pu(n,f) ongoing P. Salvador et al. 242 Pu(SF) 240 Pu(SF)
IRMM 240,242 Pu(n,f) ongoing P. Salvador et al. 242 Pu 240 Pu
Other experimental results
Response / (1/ns) Response / (1/ns) IRMM Cd RRR S. Kopecky, P. Schillebeeckx Experiments at GELINA with natural Cd samples An ENDF-6 compatible evaluation for Cd-isotopes in the RRR Data Literature data Experiments at GELINA Spin assignment etc 10 2 B(t) = B o + B g (t) + B n (t) 10 1 10 0 B o B g (t) B n (t) Transmission 10 4 nat Cd (0.03 mm) 208 Pb (0.5 mm) no sample ambient 10 3 10-1 10-2 10-3 10 2 10 1 10-4 10 3 10 4 10 5 10 6 10 7 Time-of-flight / ns Capture 10 0 10 4 10 5 10 6 10 7 Time-of-flight / ns
Transmission Yield 0.2 0.1 Exp. ( 2 mm) This work JEFF 3.1.3 JENDL 4.0 ENDF/B-VII 113 Cd Improved resonance parameter from thermal up to 10 kev Impossible to describe thermal cross section and first resonance This file puts higher importance on the shape of first resonance (Cd cut-off) than on thermal cross section 0.0 360 380 400 420 440 0.6 Neutron Energy / ev 0.4 Low abundant isotopes 106,108, 116 Cd quality files adequate 114 Cd measurements with enriched sample might give improvement Covariance will be provided by CEA Cadarache 0.2 0.0 Exp. (25 mm) This work JEFF 3.1.3 JENDL 4.0 ENDF/B-VII ENDF/B-VII.1 1 10 Neutron energy / ev
Tungsten RRR Camarda et al., Phys. Rev. C, Vol. 8 num. 5, 1813-1826 (1973) Columbia Univ. Nevis synchrocyclotron Measurements on 182 W, 184 W, 186 W enriched samples and nat W Transmission measurements and Self-indication measurements Macklin et al., Nucl. Sc. Eng., Vol. 84, 98-119 (1983) capture measurements at ORELA Measurements on 182 W, 184 W, 184 W, 186 W enriched samples Transmission measurements on nat W have been performed at GELINA adjusting the resonance energy and sometimes G n These preliminary results have shown a lack of reliable resonance parameters for 183 W
Transmission Transmission Tungsten RRR 1.0 0.9 0.8 0.6 0.6 0.3 Experimental Data ENDF/B-VII this work 590 600 610 Neutron Energy [ev] Experimental Data ENDF/B-VII This work 540 570 600 Neutron Energy [ev]
(n,g) E 1/2 / (b ev 1/2 ) (n,g) E 1/2 ) / (barn ev 1/2 ) Gold URR 140 120 GELINA I GELINA II Yamamuro et al. Kazakov et al. Macklin et al. Gwin et al. Kononov et al. IAEA ENDF 160 140 120 IAEA eval. GELINA 12 m GELINA 30 m ntof 100 100 80 20 40 60 80 100 Neutron Energy / kev 80 0 20000 40000 60000 80000 Neutron Energy / ev
Li(p,n) spectrum at threshold and Au(n,g) semi-macs Feinberg et al. (IRMM, SOREQ, Hebrew university)
Li(p,n) spectrum at threshold and Au(n,g) semi-macs Feinberg et al. (IRMM, SOREQ, Hebrew university, accept. PRC) 2.06 m gold degrader Ratynski & Käppeler PRC37(1988)595 kt=25: 648(10) mb kt=28: 582( 9) mb
HZDR - nelbe A.R. Junghans et al.
HZDR - nelbe A.R. Junghans et al.
Conclusion Considerable amount of ongoing experimental work Institutional and national programs Supported by national and EC programs (GEDEPEON, TRAKULA, ANDES, ERINDA, EUFRAT) KAERI presentation still to come