ENTRY 30529 20090312 31373052900000001
SUBENT 30529001 20090312 31373052900100001
BIB 14 36 3052900100002
INSTITUTE (3CHFSHI) 3052900100003
(3CHFTHU) 1st author's address. 3052900100004
REFERENCE (J,NSF,16,(6),71,197906) 3052900100005
AUTHOR (C.H.King,C.F.Ai,J.C.Chou) 3052900100006
TITLE Cross-section measurement for the reaction Zn-64(n,p) 3052900100007
Cu-64. 3052900100008
FACILITY (VDG,3CHFSHI) 7 MV Van de Graaff accelerator. 3052900100009
INC-SOURCE (P-LI7) 3052900100010
SAMPLE Zn metal, 99.99% purity. The content of Cu in 3052900100011
zinc rod is less than 5 ppm. Natural. 3052900100012
Disks of 2.54 cm in diam. and 0.5 cm in thickness. 3052900100013
METHOD (ACTIV) Activation. 3052900100014
.Neutron flux was measured with a proton recoil tele- 3052900100015
scope. (Radiators of 2.8 to 5.2 mg/cm2 were employed) 3052900100016
DETECTOR (GELI) 3052900100017
MONITOR (1-H-1(N,EL)1-H-1,,SIG) 3052900100018
STATUS (TABLE) Data taken from Tbl. 2 of Nucl.Sci.J.16(1979)713052900100019
CORRECTION Corrected for gamma self-absorption effect,geometric 3052900100020
factor, neutron attenuation. 3052900100021
ERR-ANALYS (ERR-T) Total error is given. The major sources of 3052900100022
error are the following (in percent) 3052900100023
(ERR-S) Count.stat.in recoil proton 1. 3052900100024
(ERR-1) Sample distance 2. 3052900100025
(ERR-2) Gamma detector efficiency 3. 3052900100026
(ERR-3) Geometry of telescope 1. 3052900100027
(ERR-4) Thickness of radiator 1. 3052900100028
(ERR-5) Total n-p scattering x-section of radiator 0.5 3052900100029
(ERR-6) Neutron angular distribution 1. 3052900100030
(ERR-7) Neutron yield 1. 3052900100031
(ERR-8) Multiple scattering correction 2. 3052900100032
(ERR-9) Gamma self-absorption correction 2. 3052900100033
Count.stat.in gamma measurement 1. to 1.5 3052900100034
Total root-mean-square error = 5.3% 3052900100035
HISTORY (19800118C) KO. 3052900100036
(20090312A) SD:Updated to new date formats,lower case, 3052900100037
made formal corrections. 3052900100038
ENDBIB 36 0 3052900100039
COMMON 10 6 3052900100040
ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 3052900100041
ERR-6 ERR-7 ERR-8 ERR-9 3052900100042
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3052900100043
PER-CENT PER-CENT PER-CENT PER-CENT 3052900100044
1.0 2.0 3.0 1.0 1.0 0.5 3052900100045
1.0 1.0 2.0 2.0 3052900100046
ENDCOMMON 6 0 3052900100047
ENDSUBENT 46 0 3052900199999
SUBENT 30529002 20090312 31373052900200001
BIB 3 5 3052900200002
REACTION (30-ZN-64(N,P)29-CU-64,,SIG) 3052900200003
DECAY-DATA (29-CU-64,12.9HR,AR,511.) 3052900200004
COMMENT The U-235 fission spectrum averaged cross section is 3052900200005
calculated to be 33.5 mb. The energy-dependent Watt 3052900200006
formalism was used as the spectrum. 3052900200007
ENDBIB 5 0 3052900200008
NOCOMMON 0 0 3052900200009
DATA 4 18 3052900200010
EN EN-RSL DATA ERR-T 3052900200011
MEV MEV MB MB 3052900200012
2.1200E+00 4.0000E-02 6.2000E+00 3.0000E-01 3052900200013
2.2200E+00 4.0000E-02 1.5700E+01 8.0000E-01 3052900200014
2.5300E+00 4.0000E-02 2.8200E+01 1.5000E+00 3052900200015
2.6300E+00 4.0000E-02 3.6800E+01 2.0000E+00 3052900200016
2.8300E+00 4.0000E-02 5.9600E+01 3.1000E+00 3052900200017
3.0300E+00 5.0000E-02 8.0500E+01 4.3000E+00 3052900200018
3.1300E+00 5.0000E-02 9.0500E+01 4.8000E+00 3052900200019
3.3300E+00 5.0000E-02 1.0260E+02 5.4000E+00 3052900200020
3.6300E+00 5.0000E-02 1.2010E+02 6.4000E+00 3052900200021
3.8300E+00 5.0000E-02 1.2880E+02 6.8000E+00 3052900200022
3.9300E+00 5.0000E-02 1.3080E+02 7.0000E+00 3052900200023
4.0200E+00 5.0000E-02 1.3920E+02 7.4000E+00 3052900200024
4.2300E+00 5.0000E-02 1.4450E+02 7.7000E+00 3052900200025
4.3300E+00 5.0000E-02 1.4550E+02 7.7000E+00 3052900200026
4.4400E+00 5.0000E-02 1.4990E+02 8.0000E+00 3052900200027
4.5400E+00 5.0000E-02 1.5050E+02 8.0000E+00 3052900200028
4.6700E+00 5.0000E-02 1.4770E+02 7.8000E+00 3052900200029
4.8400E+00 5.0000E-02 1.5480E+02 8.2000E+00 3052900200030
ENDDATA 20 0 3052900200031
ENDSUBENT 30 0 3052900299999
ENDENTRY 2 0 3052999999999