ENTRY 21502 20101114 22252150200000001
SUBENT 21502001 20101114 22252150200100001
BIB 13 22 2150200100002
INSTITUTE (2FR GRE) C.E.N.G., Service des piles. 2150200100003
REFERENCE (P,EANDC(E)-57,172,196502) 2150200100004
AUTHOR (R.Lloret) 2150200100005
TITLE -Calibration of threshold detectors (titanium, 2150200100006
iron, copper) by the ratio to nickel.- 2150200100007
(In French).- 2150200100008
FACILITY (REAC,2FR GRE) Reactor SILOE of CENG. 2150200100009
INC-SOURCE (REAC ) 2150200100010
SAMPLE .No details. 2150200100011
METHOD (ACTIV) Activation analysis. 2150200100012
DETECTOR .No details given. 2150200100013
MONITOR (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 2150200100014
ERR-ANALYS .Not given. 2150200100015
STATUS (NDD ) Data taken from NEUDADA. 2150200100016
(TABLE) Text of P,EANDC(E)-57,172,1965 2150200100017
HISTORY (19800408T) G.C. 2150200100018
(19800429E) 2150200100019
(20101114A) SD:Updated to new date formats,lower case. 2150200100020
corrected according to last EXFOR rules and Dict. 2150200100021
Code SUM deleted from REACTION (Subents 002,003) 2150200100022
and MONITOR (Subent 001) 2150200100023
STATUS and HISTORY deleted from Subents 002-004 2150200100024
ENDBIB 22 0 2150200100025
COMMON 2 3 2150200100026
EN-DUMMY MONIT 2150200100027
MEV MB 2150200100028
1.5 9.0600E+01 2150200100029
ENDCOMMON 3 0 2150200100030
ENDSUBENT 29 0 2150200199999
SUBENT 21502002 20101114 22252150200200001
BIB 2 2 2150200200002
REACTION (22-TI-46(N,P)21-SC-46,,SIG,,FIS) 2150200200003
INC-SPECT Fission neutrons of reactor. 2150200200004
ENDBIB 2 0 2150200200005
NOCOMMON 0 0 2150200200006
DATA 1 1 2150200200007
DATA 2150200200008
MB 2150200200009
8.7000E+00 2150200200010
ENDDATA 3 0 2150200200011
ENDSUBENT 10 0 2150200299999
SUBENT 21502003 20101114 22252150200300001
BIB 2 2 2150200300002
REACTION (29-CU-63(N,A)27-CO-60,,SIG,,FIS) 2150200300003
INC-SPECT Fission neutrons from reactor. 2150200300004
ENDBIB 2 0 2150200300005
NOCOMMON 0 0 2150200300006
DATA 1 1 2150200300007
DATA 2150200300008
MB 2150200300009
4.4000E-01 2150200300010
ENDDATA 3 0 2150200300011
ENDSUBENT 10 0 2150200399999
SUBENT 21502004 20101114 22252150200400001
BIB 2 2 2150200400002
REACTION (26-FE-54(N,P)25-MN-54,,SIG,,FIS) 2150200400003
INC-SPECT Fission neutrons from reactor. 2150200400004
ENDBIB 2 0 2150200400005
NOCOMMON 0 0 2150200400006
DATA 2 1 2150200400007
DATA DATA-ERR 2150200400008
MB MB 2150200400009
7.9000E+01 8.0000E+00 2150200400010
ENDDATA 3 0 2150200400011
ENDSUBENT 10 0 2150200499999
ENDENTRY 4 0 2150299999999