ENTRY 14480 20170926 14381448000000001
SUBENT 14480001 20170926 14381448000100001
BIB 15 71 1448000100002
TITLE Measurement of the 209Bi(n,4n)206Bi and 1448000100003
169Tm(n,3n)167Tm cross sections between 23.5 and 30.5 1448000100004
MeV relevant to reaction-in-flight neutron studies at 1448000100005
the National Ignition Facility 1448000100006
AUTHOR (M.E.Gooden,T.A.Bredeweg,B.Champine,D.C.Combs,S.Finch, 1448000100007
A.Hayes-Sterbenz,E.Henry,Krishichayan,R.Rundberg, 1448000100008
W.Tornow,J.Wilhelmy,C.Yeamans) 1448000100009
INSTITUTE (1USALAS,1USAUCX,1USANCS,1USATNL,1USADKE,1USALRL) 1448000100010
REFERENCE (J,PR/C,96,024622,2017) 1448000100011
FACILITY (VDGT,1USATNL)The measurements were performed using 1448000100012
the 10 MV FN tandem Van De Graaff accelerator at the 1448000100013
Triangle Universities Nuclear Laboratory 1448000100014
SAMPLE The bismuth targets were 0.9525mm in diameter and 1mm 1448000100015
thick, while the thulium foils were the same diameter 1448000100016
but 0.1 mm thick. The foils were stacked (Tm/Bi) and 1448000100017
placed approx. 16 mm from the outer flange of the 1448000100018
gas-cell assembly, with the thulium foil nearest the 1448000100019
neutron production target. Following foils were used 1448000100020
in measurement 1448000100021
Energy (MeV) Bi(mg) Tm(mg) 1448000100022
23.5+-0.105 0.7393 0.0681 1448000100023
24.9+-0.130 0.7436 0.0680 1448000100024
25.6+-0.133 0.7355 0.0670 1448000100025
26.5+-0.138 0.7416 0.0684 1448000100026
27.5+-0.142 0.7386 0.0688 1448000100027
28.5+-0.147 0.7393 0.0683 1448000100028
29.5+-0.156 0.6833 0.0695 1448000100029
30.5+-0.165 0.6833 0.0684 1448000100030
DETECTOR (HPGE)After irradiation, the foils were mounted in 1448000100031
front of lead-shielded high-purity germanium (HPGe) 1448000100032
detectors for gamma-ray counting for approx. 24 h. The 1448000100033
bismuth foils were counted at 2.5 cm from the face of 1448000100034
one HPGe detector, while the Tm foils were counted at 1448000100035
5 cm on a separate, but nearly identical, HPGe 1448000100036
detector. 1448000100037
(HPGE)Due to the long half-life of the reference 1448000100038
reaction used (31.55 yr), the bismuth samples were 1448000100039
returned to LANL and counted on the Compton 1448000100040
suppressed dual-clover HPGe detector system, which 1448000100041
has significantly higher efficiency than the other 1448000100042
HPGe detectors. 1448000100043
METHOD (ACTIV) 1448000100044
MONITOR (83-BI-209(N,3N)83-BI-207,,SIG) 1448000100045
DECAY-MON (83-BI-207,31.55YR) 1448000100046
MONIT-REF (,E.M.Zsolnay+,R,INDC(NDS)-0616,2012) 1448000100047
(,K.I.Zolotarev,R,INDC(NDS)-0584,2010) 1448000100048
INC-SOURCE (D-T) Quasimonoenergetic neutrons were produced with 1448000100049
the 3H(d,n)4He reaction. Accelerated deuterons were 1448000100050
incident onto a neutron production target consisting 1448000100051
of 2.1 Ci tritium absorbed onto a 19 mm diameter 1448000100052
deposit of titanium on a 0.4 mm thick Cu backing. 1448000100053
Neutron energy was measured using neutron 1448000100054
time-of-flight. Neutron spectrum showed main peak and 1448000100055
a group of low energy off-energy neutrons. 1448000100056
CORRECTION Corrected for contribution of off-energy neutrons. 1448000100057
Corrections ranged from 0.1% for 23 MeV neutrons and 1448000100058
almost 50% for 30 MeV neutrons 1448000100059
ERR-ANALYS (ERR-1,,0.02) Syst. uncertainty in target mass 1448000100060
(ERR-2,0.1,3.5)Syst. uncertainty in peak area 1448000100061
(ERR-3,1.19,1.42)Syst. uncertainty in gamma 1448000100062
ray efficiency 1448000100063
(ERR-4) Syst. uncertainty in neutron intensity 1448000100064
fluctuation 1448000100065
(ERR-5,3.,5.)Syst. uncertainty in Neutron monitor 1448000100066
efficiency 1448000100067
(ERR-6,0.1,3.8)Syst. uncertainty in gamma-ray emission 1448000100068
probability 1448000100069
(ERR-7,0.1,3.8)Syst. uncertainty in flux monitor cross 1448000100070
sections 1448000100071
(ERR-T) Total uncertainty at 1 sigma level 1448000100072
HISTORY (20170926C) Compiled by S.H. 1448000100073
ENDBIB 71 0 1448000100074
COMMON 1 3 1448000100075
ERR-4 1448000100076
PER-CENT 1448000100077
0.1 1448000100078
ENDCOMMON 3 0 1448000100079
ENDSUBENT 78 0 1448000199999
SUBENT 14480002 20170926 14381448000200001
BIB 2 2 1448000200002
REACTION (83-BI-209(N,4N)83-BI-206,,SIG) 1448000200003
STATUS (TABLE) Data taken from tab. 4. of the reference 1448000200004
ENDBIB 2 0 1448000200005
NOCOMMON 0 0 1448000200006
DATA 4 8 1448000200007
EN EN-RSL DATA ERR-T 1448000200008
MEV MEV B B 1448000200009
23.9 0.105 0.00022 0.00002 1448000200010
24.9 0.130 0.015 0.001 1448000200011
25.5 0.133 0.047 0.004 1448000200012
26.5 0.138 0.182 0.016 1448000200013
27.5 0.142 0.438 0.041 1448000200014
28.5 0.147 0.785 0.107 1448000200015
29.5 0.156 0.826 0.095 1448000200016
30.5 0.165 0.995 0.162 1448000200017
ENDDATA 10 0 1448000200018
ENDSUBENT 17 0 1448000299999
SUBENT 14480003 20170926 14381448000300001
BIB 2 2 1448000300002
REACTION (69-TM-169(N,3N)69-TM-167,,SIG) 1448000300003
STATUS (TABLE) Data taken from tab. 4. of the reference 1448000300004
ENDBIB 2 0 1448000300005
NOCOMMON 0 0 1448000300006
DATA 4 8 1448000300007
EN EN-RSL DATA ERR-T 1448000300008
MEV MEV B B 1448000300009
23.9 0.105 1.78 0.12 1448000300010
24.9 0.130 1.65 0.07 1448000300011
25.5 0.133 1.73 0.08 1448000300012
26.5 0.138 1.78 0.08 1448000300013
27.5 0.142 1.86 0.09 1448000300014
28.5 0.147 1.74 0.09 1448000300015
29.5 0.156 1.21 0.08 1448000300016
30.5 0.165 1.24 0.21 1448000300017
ENDDATA 10 0 1448000300018
ENDSUBENT 17 0 1448000399999
ENDENTRY 3 0 1448099999999