Japanese Activities in Nuclear Data Measurement Masayuki IGASHIRA - PowerPoint PPT Presentation

Japanese Activities in Nuclear Data Measurement Masayuki IGASHIRA Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology

Nuclear Data Projects in Japan ◎ Previous Project (2002.12-2007.3) Measurement, Evaluation, Utilization System ・ Capture Measurement at KURRI Tokyo Tech (TIT), JAEA (JAERI, JNC), KURRI ・ Fission Measurement at KURRI & Tohoku Tohoku, KURRI

Nuclear Data Projects in Japan ◎ Current Project (2005.12-2010.3) Measurement, Evaluation, Sensitivity Analysis System, Benchmark Calculation ・ Capture Measurement at J-PARC, etc. Hokkaido, Tokyo Tech, JAEA, KURRI ・ Fission Measurement at KURRI & Tohoku Tohoku, KURRI ・ Photo Nuclear Reaction Measurement at AIST JAEA, Konan, AIST ・ Decay Data Measurement at JAEA & KURRI Nagoya, JAEA

Nuclear Data Projects in Japan ◎ Previous Project (2002.12-2007.3) ・ Capture: Np-237, Am-241, 243 ・ Fission: Np-237, Am-241, 242m, 243 ◎ Current Project (2005.12-2010.3) ・ Capture: Cm-244, 246, LLFP ・ Photo Nuclear Reaction: Se-80, etc. ・ Fission: Cm isotopes, etc. ・ Decay Data: U-238, etc.

Construction of a Beam Line at J-PARC MLF • Neutron-Nucleus Reaction Instrument (NNRI) • NNRI has been completed, and spectrometers will be placed in August and November. • The first proton beam impinged the Hg target on May 30, 2008. (single pulse: 0.4 T protons) • Beam line tests are scheduled in June, September, and October. • Capture measurement will start in December. Cm-244, 246, LLFP

Capture & Photo Nuclear Reaction 1. JAEA, Konan, AIST 2. Kyushu & KURRI 3. KURRI, JAEA, Tokyo Tech 4. Tokyo Tech

JAEA Measurements of neutron capture cross sections of MA and LLFP Thermal neutron Resonance region Fast neutron region region Recent results by R&D is going on using Yayoi’s fast neutrons by Recent results by TOF method using 4 p Ge spectrometer activation method: 237 Np activation method: and 4 p BGO 237,238 Np, 241,243 Am, under analyses 80 Se spectrometer at Kyoto linac: R&D is going on using 237 Np, 241 Am Recent results by proton induced neutrons, prompt γ method: e.g. 7 Li(p, n) 7 Be by TOF 107 Pd, 91,93 Zr Examples of recent results Half life Previous us data JAEA data Refer erence ences 1.3 < s 0 < 4 4 b s 0 ＝ 0.63 63±0.02 .02 b 93 93 Zr 10 6 ｙ Zr 1.53×10 1.53 JNST, 44, 21 (2007) (Pomerance erance 1952) (Lower er Limit) 1.8±0.2 1.8 0.2 b s 0 ＝ 9.16 16±0.27 .27 b 107 Pd 107 Pd 6.5 6.5×10 10 6 ｙ JNST, 44,103 (2007) (Mughabgha habghab b 1981) (Lower er Limit)

Measurements of photon induced Measurements of thermal neutron cross sections using capture cross sections using Laser Compton scattering (LCS) photons Multiple Prompt Gamma-ray Detector and High-resolution High-energy photon Apparatus, STELLA, at JAEA JRR-3 Spectrometer, HHS, at AIST 1) Nuclear level construction: 1) Precise measurements of ( g , n) cross Demonstration for 15 N, 27 Mg, etc. sections: Recent results for 152 Sm 2) Identification of ground-state 2) High resolution measurements of ( g , transitions: 62 Ni, etc. abs) cross sections: 28 Si et al. 3) Precise measurements of thermal 3) Precise measurements of photo- neutron capture cross sections: on atomic cross sections: on going going

Inclusive ( g , X) Cross Sections Difficult-to-measure nuclei: 129 I, 3 H, 14 C, ... ( b Kyushu Univ.& KURRI emitter) Change b emitter to g emitter Application to non-destructive assay of nuclear g ray spectrum for 129 I( g , n) 128 I waste and 129 I(n, g ) 130 I Kyoto Univ. Electron Linac Facility 30 MeV e - + Ta or Pt target Bremsstrahlung X ray (continuous energy) 129 I, 99 Tc, 238 U, 88 Y, 90 Zr, 93 Nb Sample: 128 I Detector: Ge detector 130 I

1.0 Tokyo Tech Present 0.9 JENDL-3.3 ENDFB/VII.0 0.8 Sn & Se Isotopes (Sn-126, Se-79) ENDFB/VI-8.0 Capture Cross Section [b] 0.7 Cross Sections Gamma-Ray Spectra 0.6 0.5 Se-77  0.4 0.3 0.2 0.1 1 10 10 20 30 40 50 60 70 80 90 100 Present JENDL-3.3 Energy [keV] ENDFB/VII.0 ENDFB/VI-8.0 Capture Cross Section [b] Siddappa* (1972) 0 10 Dillmann* (2006) Trofimov* (1986)  Se-74 -1 10 -2 10 10 100 1000 Energy [keV]

1 10 0 10 Capture gamma-ray g -ray/Capture/MeV spectrum of Se-77 -1 10 -2 10 -3 10 0 2 4 6 8 10 12 1 10 g -ray Energy [MeV] g -ray/Capture/MeV 0 10 -1 10 Capture gamma-ray -2 10 spectrum of Se-74 -3 10 0 2 4 6 8 10 g -ray Energy [MeV]

Fission Tohoku University & KURRI

Decay Data Nagoya University & JAEA

Beta-decay energy ( Q b ) measurements of fission products by development of total absorption detector For Q b determination for new- 1 st st : Large volume BGO detectors isotopes, 3 types total absorption (12cm φ × 10cm t × 2) detectors have been developed. 10 6 放射線源 ISOMER 162Eu BG 10 5 Subtracted b 1 162 Eu 10 4 In total absorption Counts 10 3 Q b E 1 spectrum, the BGO b 2 10 2 PMT g 1 highest energy 10 1 point indicates the 100 mm 0 10 0 20 40 60 80 100 120 140 Energy 0 Q b . determination of Q b for fission products of 238 U(p,f) with on-line mass separator Objective: Q b determination new isotopes !! without decay 163-165 Eu, 166 Tb, Counts per energy scheme etc. information of E.Phys.J. A 34, New isotopes!! b  g (2007)  363-370. b  High efficiency, but energy 0 E 1 Q b resolution is ~60~100 keV Energy

Others 1. Kyushu University (n,xn), (p,xp) 2. Osaka University & JAEA DDX of a -particle emission

(n, xn) DDX @ LANSCE LANSCE WNR: Spallation neutron source (< 800 MeV) Sample: Thin C, Al, Fe, In, Pb Kyushu Univ.& LANL Thick Fe, Pb Detector: NE213, Phoswich type NaI(Tl) 140 - 160 MeV, Fe(n,xn) Incident neutron: TOF Outgoing neutron: Unfolding unfolding using moving source model

Kyushu Univ. Experiments at RCNP and JINR (Russia)  Measurement of charged particle production cross sections at 300- 600MeV with crystal detectors RCNP JINR DDX of 208 Pb(p,xp’) reaction NIRS

Experiments at HIMAC, NIRS  Development of innovative detector systems for medical application  Medical data measurement at 200-400 MeV/u proton deuteron triton MWPC GEM Flight path Continuous p , d , t , etc. D E-E part LYSO Lead (5cm) LYSO NE213 ( D E ) NE213 NE213 (Collimator) D E-E-TOF detector system

Recent activities of Osaka University group I. Murata, H. Miyamaru, K. Kondo* Division of Electric, Electronic and Information Engineering, Graduate School of Engineering, Osaka University under the collaboration with FNS group of JAEA ・ Nuclear data measurements for fusion reactor development have been carried out with a pencil-beam DT neutron source of FNS, JAEA. ・ Precise α -particle emission double differential cross section (DDXα) for carbon has been measured. ・ The branching ratio has been determined based on the kinematics analysis of the experimental results including the DDXn data by Takahashi et al. * Post doctoral fellow of JAEA from 2008 April.

Experimental arrangement for α emission DDX measurement Energy: 14.2 MeV FNS facility of JAEA Flux: 6 × 10 5 n/s/cm 2 Background flux is kept around several Polyethylene tens n/s/cm 2 ! Pre-collimator Fe Pb Ti-T target 2cm- f neutron beam Vacuum Chamber D + beam 200cm 350keV 20mA(max.) q emission Concrete Wall Sample

Obtained DDXα for carbon a 0 3 10 Present expt. 2 10 R.C.Haight et al. [mb/sr/MeV] 1 10 DDX 100 0 ADX [mb/sr] 10 -1 10 15deg. 10 20deg. 30deg. 12 C(n,n'+3 a ) 40deg. 50deg. 70deg. E a  1.0 MeV 0 90deg. 1 2 3 110deg. 4 1 5 a - p 130deg. a 6 r t i c l e 7 e -1.0 -0.5 0.0 0.5 1.0 n e r g 8 y 150deg. [ M 9 e V ] 10 Emission angle in LAB system [cos unit] 100 GS GS 100 2.43 4.7 2.43 DDX [mb/sr/MeV] DDX [mb/sr/MeV] 10 10 1 70 deg. 1 20 deg. Present expt. Present expt. R.C.Haight et al. R.C.Haight et al. 0.1 0.1 0 2 4 6 8 10 0 2 4 6 8 10 a -particle energy [MeV] a -particle energy [MeV]

Reaction kinematics analysis with Monte Carlo technique for the 12 C(n,n’+3 a ) reaction ● Aim at experimental determination of the branching ratio for inelastic scattering of 12 C and 12 C(n, a ) 9 Be* reactions. ● The branching ratio was determined by fitting measured DDX a (Present) and DDXn (by Takahashi et al.). 30 deg. 30 deg. a -particles neutrons 2 2 10 10 12 C*(9.64) Measurement B. ratio 9 Be*(2.43) SUM 36% 12 C*(7.65) 9 Be*(2.43) DDX [mb/sr/MeV] 9 Be*(4.7) 1 1 10 10 4% 12 C*(7.65) 34% 12 C*(9.64) 13% 12 C*(10.3) 6% 0 0 10 10 12 C*(10.84) 6% 12 C*(11.83) 9 Be*(4.7) Can contribute to -1 -1 nuclear data 10 10 0 2 4 6 0 2 4 6 evaluation and nuclear a -particle energy [MeV] Neutron energy [MeV] model construction