Neutron Cross-Section Measurements from ORELA

Neutron Cross-Section Measurements from ORELA K.H. Guber, Oak Ridge National Laboratory, Oak Ridge, TN, USA

ORELA 0.100 0.075 ORELA data Nuclear Astrophysics σ(n,γ) (b) 0.050 0.025 0.000 50 51 52 53 54 55 56 57 58 59 60 Energy (kev) Applications Basic Science ORNL Data Support for Nuclear Applications Computational modeling Evaluated Nuclear Data Files (ENDF/B) SAMMY Cross-Section Evaluations AMPX

OakRidgeElectronLinearAccelerator High intensity, pulsed neutron, positron and γ-ray source Four section, L-band electron linear accelerator, Peak current: 40 amps, Electron energy: 180 MeV, Rep. rate: 1-1000 Hz, Pulse width: 2-30 nsec, Power on target: 60 kw maximum Neutron production: 10 14 n/sec, 10 11 n/pulse, Positron production: 10 8 e + /sec Facility capabilities: simultaneous experiments at different flight - paths (10), -stations (18), and - lengths (9-200m, underground). Klystron e - -Gun

High flux (10 14 n/sec) => gramsized, affordable samples Excellent resolution ( t=2-30 ns) => good S/N facilitates better evaluations White neutron spectrum from E n ~ 0.01 ev - 80 MeV => reduces systematic uncertainties Measurement systems and backgrounds well understood => very accurate data Simultaneous measurements => (n,γ), (n,α), (n,n ), (n,f), and σ total experiments at the same time on different beam lines Measurements on over 180 Isotopes: ORELA measurements have contributed to ~80% of U.S. Evaluated Nuclear Data File (ENDF/B) evaluations OakRidgeElectronLinearAccelerator

(n,γ) (n,α ) (n,γ) Neutron Scatterin g @200m Transmission 18,80,200m

ORELA Flux n/sec/sr/kw 10 11 10 10 10 9 10 8 10 7 10 6 Transmission 80m, 200m Flight Path,Ta or Be Target 18m Flight Path Ta+Poly Capture 40m Flight Path, FP7 and FP6 Fission 80m, 200m Flight Path,Ta or Be Target 18m Flight Path Ta+Poly (n,α),(n,p) 9 m Flight Path Opportunities Scattering 200m Flight Path, Ta or Be Target Inelastic scattering 4πBaF 2, (n,γ),α, γ-ray -multiplicity and -production 10 5 10-3 10-2 10-1 10 0 10 1 10 2 10 3 10 4 10 5 10 6 10 7 10 8 Neutron Energy (ev) Capabilities

Experiment Requirements Duration: ~ week R = nσφε + R bkg. Maximize n, φ, and ε, minimize R bkg. Except: minimize n because samples can be expensive (enriched isotopes) and radioactive samples contribute to background. Increasing ε may lead to worse background. Increasing φ may lead to counting-rate problems. Minimize R bkg, especially sample-dependent part. Measure as much as possible (e.g. σ t, standards).

Experimental Techniques Type White Source Monoenergetic Facilities Van de Graaff, Electron and Proton Linacs, Lead Slowing- Down Spectrometer Van de Graaff, Reactor, Electron Linac Pros All energies at once. Wide energy range. Moderate to high flux. Excellent to modest resolution. Simultaneous experiments. More information (e.g. resonance parameters). High flux. Simpler experiments. Activation and quasi-maxwellian spectrum possible. Cons Backgrounds may be more troublesome: γ-flash, neutron sensitivity and other sampledependent backgrounds. More complicated analysis. Only one energy and one experiment at a time. Poor or no resolution.

Neutron Capture and Total Cross Section Experiments at a White Neutron Source: Time-of-flight technique Electron B Neutrons Neutron Production Target Capture Setup at ORELA Filters 40 m Sample Collimator Deuterated Benzene Detectors used to determine incident neutron energy. Clocks used have typically 1nsec resolution. Pulsed electron beam starts clock. γ-ray or neutron detector stops clock. Electron Neutrons Neutron Production Target 9 m Transmission Setup at ORELA Filters T.O.F. Collimator Blank Sample 80 m T.O.F. 6 Li-glass Detector v n = L/t E n = m n v 2 /2 Filters used to reduce frame-overlap background from low-energy neutrons and to reduce γ-flash effects.

Facility Parameters United States Europe ORELA LANSCE IPNS RPI GELINA n_tof Source e - linac p spallation p spallation e - linac e - linac p spallation Particle E 140 800 450 >60 120 20000 (MeV) Flight Path (m) 10-200 7-55 ~6-20 10-250 8-400 185 Pulse Width 2-30 125 70-80 15-5000 1-2000 7 (ns) Max Power 50 64 6.3 >10 11 45 (kw) Rep Rate (Hz) 1-1000 20 30 1-500 Up to 900 0.278-0.42 Best Intrinsic Resolution (ns/m) Cross-Section Measurement Facilities 0.01 3.9 3.5 0.06 0.0025 0.034 Neutrons/s 1 10 14 7.5 10 15 8.1 10 14 4 10 13 3.2 10 13 8.1 10 14

Facilities Comparison for 20m Flight path ORELA GELINA LANSCE IPNS n_tof Hypothetical Flight path length [m] 20 20 20 20 20 Pulse width [ns] 24 1 125 80 7 Power [kw] 50 11 64 6.3 45 Repetition Rate [Hz] 1000 800 20 30 0.42 Neutron Flux @ 1keV [neutron/s/cm2/ev] 2.50E+01 1.00E+01 1.20E+02 1.00E+02 2.50E+02 Neutron Flux @ 1keV [neutron/s/cm2] 2.50E+04 1.00E+04 1.20E+05 1.00E+05 2.50E+05 Intrinsic Resolution [ns/m] 1.2 0.05 6.25 4 0.35 Realistic Resolution de@ 1keV [ev] 0.97 0.98 3.48 2.25 4.49 FOM @ 1keV (Flux/(dE/E)^2) [n/s/cm2] 2.67E+10 2.60E+10 9.93E+09 1.97E+10 1.24E+10

Neutron Cross-Section Measurements In The Resolved Resonance Range Neutron flux is important but alone cannot guarantee accurate measurements. Neutron Energy resolution is important. Goal to resolve many resonances in order to obtain reliable average resonance parameters. These are important to perform the analysis of the unresolved energy range and statistical model calculations. Resolved resonances help to identify and disentangle isotopic impurities in the sample. Resolved resonances help to apply individual and no average correction to the data (self-shielding, multiplescattering).

Neutron Cross-Section Measurements 1 2 0 1 0 0 (n,γ) cross section [b] 8 0 6 0 4 0 Au(n,γ) ORELA 40m 2 0 0 1 0 0 0 1 2 0 0 1 4 0 0 1 6 0 0 1 8 0 0 2 0 0 0 N e u t r o n E n e r g y [ e V ] Au(n,γ) LANSCE 8m

10 Resolved resonances help to apply individual and no average correction to the data (self-shielding, multiplescattering). σ(n,γ)[b] 1 0.1 Multiple scattering 0.01 100 1000 10000 Energy [ev] High resolution data help to identify and disentangle isotopic impurities. Example: 192 Pt, one of the rarest isotopes in the world, only 700mg with 57% enrichment. σ(n,γ) [b] 40 30 20 10 0 192 192 192 192 192 192 ORELA Data SAMMY Fit 192 1.10 1.12 1.14 1.16 1.18 1.20 1.22 1.24 1.26 1.28 1.30 Neutron Energy [kev]

Neutron Energy Resolution Flight path length, the longer the better. Pulse width of the neutron burst, the shorter the better: Typically fixed with spallation sources (tens of ns to hundreds of ns) Linac sources can vary pulse width ( 1ns up to tens of ns). Source moderation distance The uncertainty of the creation location of the neutron inside the target/moderator has to be taken into account for the resolution function. ORELA is an undermoderated source with relatively small neutron production target. Spallation sources are usually optimized for thermal neutron flux, this requires large moderators. The moderation effect put tails on resonances due to delayed neutrons. Hinders resolution of closely spaced resonances. Produces background in unresolved energy range which cannot be corrected. This effect is of the order of 16% for 20 kev (Coceva et al. 2002) for n_tof and can not be estimated quantitatively.

Target Configuration ORELA Beryllium housing

Neutron Production GELINA NEUTRON FLIGHT PATHS NEUTRON TARGET NEUTRON MODERATOR ELECTRON BEAMLINE EXIT e - accelerated to E e-,max 140 MeV (e -, γ) Bremsstrahlung in U- target (rotating & Hgcooled) ( γ, n), ( γ, f ) in U- target Low energy neutrons by water moderator in Becanning

Neutron Production GELINA SHIELDING MODERATED SPECTRUM SHIELDING FAST SPECTRUM dϕ n /dlne n / (cm -2 s -1 ) 10 5 GELINA 30 m 800 Hz 10 4 10 3 Exp. Mod. Fast MCNP Mod. Fast Average Current : 75 µa Average Electron Energy : 100 MeV Pulse Width : 1ns Frequency : 40 800 Hz 10 2 10-2 10 0 10 2 10 4 10 6 Neutron Energy / ev PhD M. Flaska

Neutron Target n_tof Old Pb block 80cm

Neutron Energy Resolution Au(n,γ) LANSCE 8m Au(n,γ) n_tof CERN 185m 1 0 0 0 0 1 0 0 0 (n,γ) cross section [b] 1 0 0 1 0 1 0.1 1 0 0 8 0 6 0 4 0 2 0 0 4 0 5 0 6 0 7 0 8 0 Au(n,γ) ORELA 40m 4 0 5 0 6 0 7 0 8 0 N e u t r o n E n e r g y [e V ]

Superior Resolution at ORELA Results in Much Better S/N FZK 1m flight path Measured using BaF 2 ball at FZK. σ (mb) 14000 ORELA 40m flight path Measured using C 6 D 6 at ORELA. 9000 4000-1000 3.0 3.5 4.0 4.5 E n (kev)

Moderation Distance Distribution Response / (1/cm) 10 0 E n = 1-10 ev 10-1 10-2 10-3 GELINA10-1 10-4 -5 0 5 10 15 Distance / cm E 10 0 n = 100-1000 ev MCNP (PhD M. Flaska) Coceva 10-2 10-3 10-4 -5 0 5 10 15 Distance / cm n_tof 10 0 E n = 10000-30000 ev 10-1 10-2 10-3 ORELA 10-4 -5 0 5 10 15 Distance / cm The uncertainty of the creation location of the neutron inside the moderator has to be taken into account for the resolution function. This can be quite sizeable for large target and moderator assemblies. The effect is that it will put tail on the resonances in the resolved neutron energy region. Additionally it will produce a back-ground in the unresolved region which can not be corrected for. This effect is of the order of 16% for 20 kev (Coceva et al. 2002) for n_tof and can not be estimated quantitatively.

Average Moderation Distance L ( cm ) 100 ORELA n_tof 10 1 0.1 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 1.E+06 Neutron Energy (ev) Due to moderation the neutron flight path is energy dependent. L( E) = L 0 n_tof [cm]: + L L = 0. 101 ORELA [mm]: E L = 22.1 1.6 ln E + 0.283 (ln E) 2

The Influence of Resolution σ (b) 1 0-2 n _ T O F O R L E A L u j a n 1 0-3 2 5 M g ( n, γ ) SAMMY Calculations 1 0-4 1 0-5 3 0 0 4 0 0 5 0 0 6 0 0 M g 2 5 C o m p 3 0 0 t 6 0 0 A u g. 2, 2 0 0 6 1 2 : 2 2 : 3 0 P M E n ( k e V ) 6 0 0 O R E L A U 2 3 3 T o t a l a t T = 1 0 K P a t t e n d e n e t a l. 1 9 6 3 Total Cross Section (b) 5 0 0 4 0 0 3 0 0 2 0 0 1 0 0 Measured Data 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 1 0 0 E n e r g y ( e V )

n-tof (180 m) <-> GELINA (60 m) Counts/ (1/ns) [arb. units] 4 2 206 Pb(n,γ) E n = 3.36 kev GELINA 60 m n-tof 200 m 0 3.30 3.35 3.40 Neutron Energy / kev Capture Yield [arb. units] 0.015 0.010 0.005 56 Fe(n,γ) E n = 34.21 kev GELINA 60 m n-tof RPI (32-40 kev) 0.000 33.6 34.0 34.4 34.8 Neutron Energy / kev P. Schillebeeckx, IRMM

Doppler - Resolution Broadening @20 m for 241Pu 1.E+01 1.E+00 Width/Resolution 1.E-01 1.E-02 Doppler 300K Doppler 70K AvLSpacing 1.E-03 IPNS Experiment 20m, 80ns LANSCE 20m, 125ns ORELA 20m 8ns ORELA 80m 8ns 1.E-04 1.E+00 1.E+01 1.E+02 1.E+03 1.E+04 1.E+05 Energy (ev)

Trouble with Weighting Functions 20% discrepancy found in neutron width of 1.15-keV resonance in Fe measured with C 6 D 6 compared to transmission measurements. Fe cascade is hard while those for Au and Ag are soft. Corvi et al. (1988) showed that measured weighting functions could solve discrepancy. Perey et al. (1988) showed that EGS simulations agreed with 207 Pb(n,γ) cascades and that EGS-4 weighting functions also solved Fe discrepancy. Sample and surrounding material was neglected in previous weighting function calculations.

Results for 56 Fe with Weighting Functions for C 6 D 6 Detectors Exp. Type Lab Year Det.Type WeightF. gγ n Γ γ /Γ [mev] Γ n [mev] Capture Geel 1991 C 6 D 6 Experim. 56.7 ± 1.9 62.9 ± 2.1 Capture Harwell 1988 C 6 D 6 EGS4 59.5 ± 3.0 66.4 ± 3.3 Capture Oak Ridge 1988 C 6 F 6 EGS4 58.0 ± 2.9 64.5 ± 3.0 Capture Oak Ridge 1988 C 6 D 6 EGS4 56.8 ± 2.3 63.0 ± 2.5 Capture Oak Ridge 1994 C 6 D 6 EGS4 55.8 ± 1.7 61.8 ± 1.9 Transmission Oak Ridge 1985 55.7 ± 0.8 61.7 ± 0.9

Much of the Old Neutron Data (on Which Current Evaluations Are Based) Are Seriously Incorrect Some problems with the old data: Underestimated neutron sensitivity correction Low-energy cut off of 3 kev No high energy (>100 kev) data Incorrect weighting function Poor resolution Poorly characterized samples, i.e. water in the sample (n,γ) [b] 0.15 0.10 0.05 0.00 30 40 50 60 Neutron Energy [kev] ORELA Si Capture ENDF/B-VI Ex: Large neutron sensitivity of older measurements led to many erroneously-large resonance areas in current evaluations.

Modified capture data measurement system has significantly less structure Sample changer replaced C 6 F 6 Scintillator replaced Aluminum guide replaced by C-fiber tube Detector housing removed

New ORELA Weighting Functions Demonstrated to be Accurate to Better Than 3% Koehler et al./voss et al. σ (mb) 1.8 1.6 1.4 1.2 1.0 0.8 0.6 0.4 0.2 2 4 6 8 10 12 14 16 18 20 E n (kev) 250 200 150 100 50 0 Ratio of Capture Kernels for 136 Ba Koehler et al. } Voss et al. Koehler et al. Voss et al. } 134 Ba(n,γ) 136 Ba(n,γ) 2 3 4 5 6 7 8 10 2 2 3 4 E n (kev) Excellent agreement between ORELA C 6 D 6 (Koehler et al.) and FZK BaF 2 (Voss et al.) 134,136 Ba(n,γ) measurements. Hardness of cascade varies considerably from resonanceto-resonance, but no systematic difference between capture kernels observed. Excellent (<3%) agreement for average cross sections.

New 95 Mo(n,γ) experiments AGB stellar models over predict the abundance of 95 Mo compared to observation in SiC grain which origin from an AGB star where the s-process takes place. M. Lugaro et. al. 2003: calculations show a 30% enhancement in the (n,γ) cross section for 95 Mo would solve the problem.

New 95 Mo(n,γ) and σ T Measurements at the Oak Ridge Electron Linear Accelerator (ORELA) 95 Mo(n,γ) measured using new apparatus on F.P. 6 at 40 m. C 6 D 6 using PHWT. 6 Li-glass flux monitor. Separate background measurements. Modified to measure coincidence PH data. 95 Mo σ t measured on F.P. 1 at 80 m. 6 Li-glass detector. Separate sample-out, CH 2, and Bi measurements. Transmission. CINDORELA Capture of Incident Neutrons Detector at ORELA

New 95 Mo(n,γ) and σ t Data from ORELA 4 2 0 95 Mo+n 1.0 Resonance analysis using SAMMY. 318 resonances to 10 kev. Only 106 previously known. Only 32 previous firm J π assignments. Transmission data yield parity of resonance if neutron width is large enough. σ (b) 5 0 0.0 4.65 4.70 4.75 4.80 4.85 4.90 10 0 s s s s 0.0 6.50 6.55 6.60 6.65 6.70 s p p s s s s p s Data SAMMY 0.5 1.0 0.5 1.0 0.5 0.0 3.70 3.75 3.80 3.85 3.90 40 Transmission 20 Transmission = exp(-nσ t ) 0 1.0 p p s p p 0.0 0.60 0.65 0.70 0.75 0.80 E n (kev) s 0.5

The Importance of Total Cross Section Data More complete resonance parameter data will help improve nuclear statistical model. Is indispensable for obtaining the most accurate (n,γ) reaction rates. See resonances not visible in (n,γ) data. Improved self-shielding and multiple scattering corrections. Lack of good total cross section data can lead to serious errors in these corrections and hence in the cross sections. σ γ E 1/2 (mb kev 1/2 ) 850 750 650 550 450 350 116 Sn(n,γ) Koehler et al., Num. Int. Koehler et al., Resonance Wisshak et al., Num. Int. Wisshak et al., Resonance 4 5 6 7 8 9 10 1 2 E n (kev) Ex: 116 Sn Use of incorrect neutron widths led to incorrect low-energy cross sections (Wisshak et al.).

The Importance of Total Cross Section Data No high-quality σ t data available previously. Needed for accurate determination of reaction rate from resonance region because measurements made with thick samples. Compare results from pulse-height weighting technique to results from 4π BaF 2 detector. Resonance Self-Shielding Correction 136 Ba(n, γ ) Calculated by SAMMY σ γ (b) 9 8 7 6 5 4 3 2 1 Voss et al. Γ γ = 269 mev Γ n = 502 mev A γ = 351 mev "True" "Measured" Present Work Γ γ = 248 mev Γ n = 3660 mev A γ = 465 mev 0 19750 19760 19770 19780 19790 19800 19810 19820 E n (ev)

thin <--> thick transmission Determination of statistical factor g A t, thin ngγ A t ngγ Γ,thick n n Trasnmission 1.0 0.8 0.6 0.4 g= 2 Measurement FIT 2 χ ν = 2.25 t = 1.60 x 10-2 at/b Trasnmission 1.0 0.8 0.6 0.4 g = 1 Measurement FIT χ ν 2 = 0.95 t = 1.60 x 10-2 at/b g = 2J + 1 2(2I + 1) 0.2 1.0 0.8 Measurement FIT t=3.00 x 10-2 at/b 0.2 1.0 0.8 Measurement FIT t=3.00 x 10-2 at/b P. Schillebeeckx, IRMM Trasnmission 0.6 0.4 Trasnmission 0.6 0.4 0.2 25000 25500 26000 Neutron Energy / ev 0.2 25000 25500 26000 Neutron Energy / ev

Simplified schematic of neutron transmission Electron Beam Neutrons Neutron Production Target (water cooled) 9 m Transmission Setup at ORELA Filters T.O.F. Collimator Blank Sample 18 or 80 or 200 m Transmision 1.0 0.8 0.6 0.4 0.2 0.0 10 20 30 40 50 60 70 80 90 100 6 Neutron Energy [kev] Li-glass, NE110 Fission chamber For transmission, separate measurements of sample in and sample out Nσ T d T = e

New & Improved ORELA Transmission Apparatus Transient digitizer (Acqiris DC-270) replaced old CAMAC TDC and several NIM modules. Allows simultaneous measurement of time of flight and pulse height Previous system for 6 Li-glass detector was 1-D (TOF only), and for NE-110 detector had only 4 pulse-height channels. Allows simultaneous use of both types of detectors. Unlimited stops per start Previous system limited to 8 stops/start (LeCroy 4208 TDC) Fewer NIM and CAMAC modules Simpler and more reliable

Test of New Transmission Apparatus: 95 Mo 6 Li-glass detector at 80 m ORELA at 525 Hz, 8 ns pulse width and 4 kw power Computercontrolled cycling between 95 Mo, blank, Bi, and CH 2 samples Pulse Height vs. TOF vs. Counts in Region Near Black Resonance at 45 ev

(n,α) measurements for explosive nucleosynthesis calculations Improve α+nucleus potential for explosive nucleosynthesis calculations Compensated ion chamber (CIC) on FP 11, L = 8.9 m CIC suppresses γ flash. Allows measurements to much higher energies, larger samples (10 cm dia.), and high efficiency for measuring small (σ ave 10 µb) cross sections 64 Zn(n,α) meas. in progress Inside of Main CIC Detector

ORELA capture data for 41 KCl compared to JENDL3.3 Several resonance areas too large (neutron sensitivity) in evaluation 4 3 41 KCl ORELA Data JENDL Parameters capture cross section [b] 2 1 0 4 3 10 12 14 16 18 20 41 KCl ORELA Data JENDL Parameters 2 1 0 20 22 24 26 28 30 Energy [kev]

Comparison of SAMMY Fits with ORELA nat Cl transmission data

Comparison of SAMMY Fits with ORELA nat Cl capture data

200000 300000 400000 500000 600000 Recent ORELA capture data compared to evaluations Several resonance areas are too large (neutron sensitivity?) and resonances are missing in evaluations σ(n,γ) (b) 1.0 0.8 0.6 0.4 0.2 ORELA data JENDL data Al Capture Cross Section (b) 0.08 0.07 0.06 0.05 0.04 0.03 0.02 0.01 ORELA data 1999 ENDF/B-VI Si Capture Cross Section (b) 0.020 0.018 0.016 0.014 0.012 0.010 0.008 0.006 0.004 0.002 Si ORELA data 1999 ENDF/B-VI σ(n,γ) (b) 65 60 55 50 45 40 35 30 25 20 15 10 5 ORELA data ENDF data Cl 0.0 5.7 5.8 5.9 6.0 6.1 6.2 Energy (kev) 0.00 30 40 50 60 Neutron Energy (kev) 0.000 500 510 520 530 540 550 560 570 580 590 600 610 Neutron Energy (kev) 0 0.380 0.385 0.390 0.395 0.400 0.405 0.410 0.415 0.420 Energy (kev) σ(n,γ) (b) 8 6 4 2 Cl ORELA data ENDF data Capture Cross Section [b] 1 0.1 0.01 F E N D F /B V I E v a lu a tio n O R ELA Data Capture Cross Section [b] 0.007 0.006 0.005 0.004 0.003 EN D F /B VI E valua tion O R EL A D ata F 1E-3 0.002 0 4.200 4.225 4.250 4.275 4.300 En ergy (kev) 1E-4 20000 40000 60000 80000 100000 120000 140000 Energy [ev] 0.001 Energy [ev] σ(n,γ) (b) 10 8 6 4 2 ORELA data ENDF data K σ(n,γ) (b) 10 8 6 4 2 ORELA data ENDF data K σ(n,γ) (b) 4.0 3.5 3.0 2.5 2.0 1.5 1.0 K ORELA data ENDF data 0.5 0 1.10 1.11 1.12 Energy (kev) 0 2.00 2.01 2.02 2.03 2.04 2.05 2.06 Energy (kev) 0.0 9.0 9.1 9.2 9.3 9.4 9.5 9.6 9.7 9.8 9.9 1 0.0 Energy (kev)

Recent (n,γ) and Transmission for 53Cr 1 0 O R E L A d a ta E N D F - V II 1 0.0 1 1 E - 3 1 E - 4 1 1 0 N e u tr o n E n e r g y 1 0 0 [k e V ] O R E L A D a ta E N D F /B -V II 1.0 0.8 Transmission σ(n,γ) [b] 0.1 0.6 0.4 0.2 0.0 1 1 0 N e u tr o n E n e r g y 1 0 0 [k e V ]

Recent (n,γ) and Transmission for natural Ti 1. 0 0. 8 N a tu r a l T i (n,γ ) d a ta E N D F /B -V II p a r a m e te r s 0. 6 (n,γ) [b] 0. 4 0. 2 0. 0 1 1 0 1 0 0 N e u t r o n E n e r g y [ k e V ] E x p e r i m e n t a l t r a n s m i s s i o n f o r n a t u r a l T i T r a n s m i s s i o n c a l c u l a t e d f r o m E N D F / B - V I I 1. 0 Transmission 0. 5 0. 0 1 1 0 1 0 0 N e u t r o n E n e r g y [ k e V ]

Recent (n,γ) and Transmission on 48 Ti 1.0 0.9 0.8 0.7 0.6 4 8 T i ( n, γ ) E N D F /B - V II (n,γ) [b] 0.5 0.4 0.3 0.2 0.1 0.0-0.1 1. 0 0. 8 1 1 0 1 0 0 N e u t r o n E n e r g y [ k e V ] T ra n s m is s io n E N D F /B -V II p a ra m e te rs Transmission 0. 6 0. 4 0. 2 0. 0 1 1 0 1 0 0 E n e r g y [ k e V ]

Comparison of the new ORNL 58 Ni evaluation with experimental (n,γ) data 1 58 Ni (n,γ) data SAMMY fit (n,γ) [b] 0.1 0.01 10 20 30 40 50 60 70 80 90 100 Energy [kev]

Personnel ORELA: C. Ausmus, D.R. Brashear, T.S. Bigelow, K.H. Guber, J.A. Harvey, P.E. Koehler, J.A. White, D. Wiarda ORELA Personnel Nuclear Data Group: M. Dunn, G. Arbanas, K.H. Guber, H. Derrien, L.L. Leal, N.M. Larson, R.O. Sayer, D. Wiarda

Summary Neutron Energy Resolution Perform new total and capture cross section measurements for the NCSP, i.e. 63 Cu, 65 Cu, Continue nuclear astrophysics experiments Finish 95 Mo(n,γ) and σ t, 64 Zn(n,α) Future experiments include (n,γ) and σ t for 86,87 Sr and 149 Sm(n,α)

Capture and transmission are not always complementary Capture (thin): A γ Γn Γ ng Γ γ Γ γ << Γ n ngγ γ Γ γ >> Γ n ngγ n Transmission (thin): A t, thin ngγ n ngγ n complementary combine capture and transmission measurements with different sample thicknesses