ENTRY 21248 20131222 22382124800000001 SUBENT 21248001 20131222 22382124800100001 BIB 14 51 2124800100002 INSTITUTE (2SWTETH) 2124800100003 REFERENCE (J,HPA,36,298,1963) 2124800100004 (J,HPA,34,481,196108) superseded. 2124800100005 AUTHOR (F.Heinrich,F.Tanner) 2124800100006 TITLE (n,t)-reactions on medium-weight nuclei 2124800100007 FACILITY (REAC,2SWTETH) Swimming pool reactor SAPHIR, EIR. 2124800100008 INC-SOURCE (REAC ) Fission neutron spectrum from reactor core. 2124800100009 SAMPLE .Aluminium can containing cylinders of sample material 2124800100010 (metallic) plus monitor foils both with and without 2124800100011 cadmium screen (1 mm sheet). 2124800100012 METHOD (ACTIV) Determination of the absolute quantity of 2124800100013 tritium produced by irradiation of sample targets. 2124800100014 DETECTOR (GEMUC) Geiger-Mueller counter filled with 90% 2124800100015 counting gas (3 parts argon plus 1 part ethylene) 2124800100016 and 10% H(2)-HT-mixture, the latter containing the 2124800100017 tritium, extracted by heating the irradiated samples, 2124800100018 plus hydrogen carrier gas. 2124800100019 (THRES) Al and Ni foils were used as threshold 2124800100020 detectors for the determination of the absolute fast 2124800100021 neutron flux and the variations of the flux within 2124800100022 the sample packets. 2124800100023 .The tritium counter is surrounded by an annular 2124800100024 anticoincidence counter as well as by a massive 2124800100025 shielding against neutrons, cosmic rays and 2124800100026 environmental activities. 2124800100027 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG,,FIS) 2124800100028 ((MONIT2)28-NI-58(N,2N)28-NI-57,,SIG,,FIS) 2124800100029 ((MONIT3)79-AU-197(N,G)79-AU-198,,SIG) 2124800100030 .Also gold activation is used. Assumed value for cross 2124800100031 section of (79-Au-197(n,g)79-Au-198) at 2200 m/s is 2124800100032 98.8 b. 2124800100033 STATUS (TABLE) Data from VII of J,HPA,36,298,1963, the same as2124800100034 in NEUDADA. 2124800100035 CORRECTION .Corrections applied for background, effective 2124800100036 detector efficiency, sample impurities, gas losses in 2124800100037 filling the tritium counter, variations of fast 2124800100038 neutron flux in the sample container, absorption and 2124800100039 backscattering of beta particles in the samples and 2124800100040 sample holders used for the neutron flux measurements 2124800100041 ERR-ANALYS .A detailed description of error analysis is given. 2124800100042 The average total error of the given effective cross 2124800100043 sections is 15%. 2124800100044 HISTORY (19800110T) G.C. 2124800100045 (19800118E) 2124800100046 (20101114A) SD:Updated to new date formats,lower case. 2124800100047 corrected according to last EXFOR rules and Dict. 2124800100048 HISTORY and STATUS moved to Subent 001. 2124800100049 Author's name corrected (F,Tanner => F.Tanner) 2124800100050 EN-NRM3 added in COMMON 2124800100051 (20131222U) SD: Year in ref. was changed: 2124800100052 HPA,36,298,196210 -> HPA,36,298,1963 2124800100053 ENDBIB 51 0 2124800100054 COMMON 7 6 2124800100055 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR EN-NRM3 2124800100056 MONIT3 2124800100057 MEV B B B B EV 2124800100058 B 2124800100059 1.5000E+00 6.8000E-01 1.0000E-01 4.7000E+00 7.0000E-01 2.5300E-022124800100060 98.8 2124800100061 ENDCOMMON 6 0 2124800100062 ENDSUBENT 61 0 2124800199999 SUBENT 21248002 20101114 22252124800200001 BIB 2 2 2124800200002 REACTION (13-AL-27(N,T)12-MG-25,,SIG,,FIS) 2124800200003 ERR-ANALYS (DATA-ERR) total error of effective cross section 2124800200004 ENDBIB 2 0 2124800200005 NOCOMMON 0 0 2124800200006 DATA 2 1 2124800200007 DATA DATA-ERR 2124800200008 NB NB 2124800200009 2.6000E+02 4.0000E+01 2124800200010 ENDDATA 3 0 2124800200011 ENDSUBENT 10 0 2124800299999 SUBENT 21248003 20101114 22252124800300001 BIB 2 2 2124800300002 REACTION (24-CR-0(N,T),,SIG,,FIS) 2124800300003 ERR-ANALYS (DATA-ERR) total error of effective cross section 2124800300004 ENDBIB 2 0 2124800300005 NOCOMMON 0 0 2124800300006 DATA 2 1 2124800300007 DATA DATA-ERR 2124800300008 NB NB 2124800300009 6.2000E+01 1.0000E+01 2124800300010 ENDDATA 3 0 2124800300011 ENDSUBENT 10 0 2124800399999 SUBENT 21248004 20101114 22252124800400001 BIB 2 2 2124800400002 REACTION (25-MN-55(N,T)24-CR-53,,SIG,,FIS) 2124800400003 ERR-ANALYS (DATA-ERR) total error of effective cross section 2124800400004 ENDBIB 2 0 2124800400005 NOCOMMON 0 0 2124800400006 DATA 2 1 2124800400007 DATA DATA-ERR 2124800400008 NB NB 2124800400009 1.7000E+02 3.0000E+01 2124800400010 ENDDATA 3 0 2124800400011 ENDSUBENT 10 0 2124800499999 SUBENT 21248005 20101114 22252124800500001 BIB 2 2 2124800500002 REACTION (26-FE-0(N,T),,SIG,,FIS) 2124800500003 ERR-ANALYS (DATA-ERR) total error of effective cross section 2124800500004 ENDBIB 2 0 2124800500005 NOCOMMON 0 0 2124800500006 DATA 2 1 2124800500007 DATA DATA-ERR 2124800500008 NB NB 2124800500009 5.6000E+01 1.0000E+01 2124800500010 ENDDATA 3 0 2124800500011 ENDSUBENT 10 0 2124800599999 SUBENT 21248006 20101114 22252124800600001 BIB 2 3 2124800600002 REACTION (27-CO-59(N,T)26-FE-57,,SIG,,FIS) 2124800600003 Only range of the data given (50 nb < sigma < 130 nb) 2124800600004 ERR-ANALYS (DATA-ERR) total error of effective cross section 2124800600005 ENDBIB 3 0 2124800600006 NOCOMMON 0 0 2124800600007 DATA 2 1 2124800600008 DATA-MIN DATA-MAX 2124800600009 NB NB 2124800600010 5.0000E+01 1.3000E+02 2124800600011 ENDDATA 3 0 2124800600012 ENDSUBENT 11 0 2124800699999 SUBENT 21248007 20101114 22252124800700001 BIB 1 1 2124800700002 REACTION (28-NI-0(N,T),,SIG,,FIS) 2124800700003 ENDBIB 1 0 2124800700004 NOCOMMON 0 0 2124800700005 DATA 1 1 2124800700006 DATA-MAX 2124800700007 NB 2124800700008 5.0000E+01 2124800700009 ENDDATA 3 0 2124800700010 ENDSUBENT 9 0 2124800799999 SUBENT 21248008 20101114 22252124800800001 BIB 2 2 2124800800002 REACTION (29-CU-0(N,T),,SIG,,FIS) 2124800800003 ERR-ANALYS (DATA-ERR) total error of effective cross section 2124800800004 ENDBIB 2 0 2124800800005 NOCOMMON 0 0 2124800800006 DATA 2 1 2124800800007 DATA DATA-ERR 2124800800008 NB NB 2124800800009 7.3000E+01 1.0000E+01 2124800800010 ENDDATA 3 0 2124800800011 ENDSUBENT 10 0 2124800899999 SUBENT 21248009 20101114 22252124800900001 BIB 2 2 2124800900002 REACTION (47-AG-0(N,T),,SIG,,FIS) 2124800900003 ERR-ANALYS (DATA-ERR) total error of effective cross section 2124800900004 ENDBIB 2 0 2124800900005 NOCOMMON 0 0 2124800900006 DATA 2 1 2124800900007 DATA DATA-ERR 2124800900008 NB NB 2124800900009 1.9000E+01 3.0000E+00 2124800900010 ENDDATA 3 0 2124800900011 ENDSUBENT 10 0 2124800999999 ENDENTRY 9 0 2124899999999