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