ENTRY 30618 20090805 31403061800000001 SUBENT 30618001 20090805 31403061800100001 BIB 9 16 3061800100002 INSTITUTE (3CPRIHP) 3061800100003 REFERENCE (J,HFH,3,(2),113,198105) in Chinese, English abstract 3061800100004 AUTHOR (Zhao Zhenlan,Guo Yinghuan,Zhang Yuanji,Feng Xizhang) 3061800100005 TITLE The determination of Ni-65 average projectional recoi l3061800100006 ranges in Cu-65(n,p)Ni-65 reaction with 13.9-15.6 MeV 3061800100007 neutrons. 3061800100008 FACILITY (CCW,3CPRBNU) 3061800100009 INC-SOURCE (D-T) 3061800100010 SAMPLE Natural Cu disk foil, thickness about 15 mg/cm2, high 3061800100011 purity(less than 0.01% for Zn,Ga,Ni and Th. 3061800100012 U-content was less than 0.05% weight). 3061800100013 METHOD (ACTIV) Thick target-thick catcher method. (For recoil 3061800100014 range determination) 3061800100015 HISTORY (19820125C) KO. 3061800100016 (19850215U) OS. Country code corrected. 3061800100017 (20090725A) SD:Updated to new date formats,lower case. 3061800100018 ENDBIB 16 0 3061800100019 NOCOMMON 0 0 3061800100020 ENDSUBENT 19 0 3061800199999 SUBENT 30618002 20090805 31403061800200001 BIB 8 21 3061800200002 REACTION (29-CU-65(N,P)28-NI-65,,SIG,,AV) 3061800200003 INC-SPECT Neutron flux was about 5. x 10**9 n/cm2/sec. 3061800200004 Average neutron energies between 3061800200005 13.9 and 15.6 MeV. 3061800200006 Compiler's note === 3061800200007 The cross-section curve of Cu-65(n,p)Ni65 is rather 3061800200008 flat in this energy range. === 3061800200009 DETECTOR (GELI)Resolution for 1332keV gamma of Co-60 was 1.88keV3061800200010 DECAY-DATA (28-NI-65,2.56HR,DG,366.,0.0478, 3061800200011 DG,1115.,0.154, 3061800200012 DG,1482.,0.257) 3061800200013 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3061800200014 MONIT-REF (,Ma Hong-Chang+,J,CNST,2,113,1975) 3061800200015 *Compiler's note =Reference not available= 3061800200016 STATUS (TABLE) Data taken from Table 3 of 3061800200017 J.Nucl.Radiochem.(Beijing),3(1981)113 3061800200018 ERR-ANALYS (ERR-T) Error includes the following ones: 3061800200019 (ERR-1,,4.) Gamma full energy peak-area less than 4%, 3061800200020 (ERR-2) Neutron flux 2%, 3061800200021 (MONIT-ERR) Error of monitor reaction 3%, 3061800200022 (ERR-3) Detector efficiency 5%. 3061800200023 ENDBIB 21 0 3061800200024 COMMON 5 3 3061800200025 EN-NRM MONIT MONIT-ERR ERR-2 ERR-3 3061800200026 MEV MB PER-CENT PER-CENT PER-CENT 3061800200027 1.4600E+01 1.1650E+02 3.0 2.0 5.0 3061800200028 ENDCOMMON 3 0 3061800200029 DATA 4 1 3061800200030 EN-MIN EN-MAX DATA DATA-ERR 3061800200031 MEV MEV MB MB 3061800200032 1.3900E+01 1.5600E+01 2.3700E+01 2.4000E+00 3061800200033 ENDDATA 3 0 3061800200034 ENDSUBENT 33 0 3061800299999 ENDENTRY 2 0 3061899999999