ENTRY            31407   20240216                                 3140700000001 
SUBENT        31407001   20240216   20240513                      3140700100001 
BIB                 14         32                                 3140700100002 
TITLE      Activation cross section of 63Cu(n,a)60Co reaction     3140700100003 
AUTHOR     (Lu Hanlin, Zhao Wenrong, Yu Weixiang, Yuan Xialin)    3140700100004 
INSTITUTE  (3CPRAEP)                                              3140700100005 
REFERENCE  (J,CNP,12,373,1990)                                    3140700100006 
           (R,INDC(CPR)-16,1989)                                  3140700100007 
           (W,LU,199210) Final data                               3140700100008 
FACILITY   (VDG,3CPRAEP)                                          3140700100009 
           (CCW,3CPRAEP)                                          3140700100010 
INC-SOURCE (D-T) sample located at 3-6 cm from neutron source     3140700100011 
SAMPLE     Disks of 0.2 mm in thickness and 20 mm in diameter     3140700100012 
            sandwiched between two thin (0.2 mm) Al foils         3140700100013 
METHOD     (ACTIV)                                                3140700100014 
DETECTOR   (GELI)                                                 3140700100015 
MONITOR    (13-AL-27(N,A)11-NA-24,,SIG)                           3140700100016 
            Data evaluated by author. No reference for data.      3140700100017 
CORRECTION Corrected for                                          3140700100018 
            . 24Na and 60Co gamma-ray self-absorption             3140700100019 
            . 24Na and 60 Co loss due to forward recoils          3140700100020 
            . neutron fluence fluctuation during irradiation      3140700100021 
            .  finite area of samples                             3140700100022 
ERR-ANALYS (ERR-T) Principal sources of uncertainties are         3140700100023 
            . reference cross section,                            3140700100024 
            . Ge(Li) detector efficiency                          3140700100025 
            . counting statistics,                                3140700100026 
            . sample geometry,                                    3140700100027 
            . corrections,                                        3140700100028 
            . mean neutron energy determination                   3140700100029 
STATUS     (TABLE) private communication with author              3140700100030 
HISTORY    (19921102C) HW                                         3140700100031 
           (19930119U) HW.- STATUS altered.-                      3140700100032 
           (20090730U) SD: Updated to new date formats, lower case3140700100033 
           (20240216U) On. REFERENCE(CNP): Issue number deleted.  3140700100034 
ENDBIB              32          0                                 3140700100035 
NOCOMMON             0          0                                 3140700100036 
ENDSUBENT           35          0                                 3140700199999 
SUBENT        31407002   20100220                             31443140700200001 
BIB                  1          1                                 3140700200002 
REACTION   (29-CU-63(N,A)27-CO-60,,SIG)                           3140700200003 
ENDBIB               1          0                                 3140700200004 
NOCOMMON             0          0                                 3140700200005 
DATA                 6          6                                 3140700200006 
EN         EN-ERR     DATA       ERR-T      MONIT      MONIT-ERR  3140700200007 
MEV        MEV        MB         MB         MB         MB         3140700200008 
      12.82       0.45       55.1        6.3      126.9        4.33140700200009 
      14.09       0.12       50.2        1.9      121.5        1.73140700200010 
      14.58       0.17       49.0        1.7      115.5        1.63140700200011 
      14.80       0.19       46.6        1.7      113.2        1.33140700200012 
      16.86       0.90       29.3        1.4       80.9        2.03140700200013 
      17.63       0.21       23.9        1.2       69.1        1.73140700200014 
ENDDATA              8          0                                 3140700200015 
ENDSUBENT           14          0                                 3140700299999 
ENDENTRY             2          0                                 3140799999999