ENTRY 23373 20180710 22692337300000001 SUBENT 23373001 20180710 22692337300100001 BIB 15 57 2337300100002 INSTITUTE (2GERMUN) 2337300100003 REFERENCE (T,GRYNTAKIS,197603) Thesis DM-6909(1976),Technical 2337300100004 University of Munich (in German). 2337300100005 (J,JRC,46,159,1978) Authors E.M.Gryntakis, J.I.Kim . 2337300100006 Fission neutron CS of U233(n,2n), Ni60(n,p), Al27(n,p),2337300100007 and (n,g) RI for Ta181, Lu176, Ni64, Co59, Mg16 . 2337300100008 REL-REF (O,20625001,E.M.Gryntakis+,J,JRC,46,159,1978) 2337300100009 Data for (n,g) reaction. 2337300100010 AUTHOR (E.M.Gryntakis) 2337300100011 TITLE Examination of the dependence of the effective cross 2337300100012 section from the neutron temperature, measurements 2337300100013 of the neutron temperature and determination of some 2337300100014 cross sections for neutron capture and neutron 2337300100015 fission 2337300100016 FACILITY (REAC,2GERMUN) 2337300100017 INC-SOURCE (REAC) Pneumatic positions,reflector and rotating 2337300100018 disk facility of FRM-reactor in Munich. 2337300100019 INC-SPECT . Reactor fast neutron spectrum. 2337300100020 METHOD (ACTIV) Activation. 2337300100021 DETECTOR (GELI) Ge(Li)-detectors coupled to a ND4420 analyzer. 2337300100022 (SCIN) The alpha activity of alpha emitters was 2337300100023 measured with a home-made liquid scintillation 2337300100024 counter. 2337300100025 MONITOR 3 reactions used for incident fission neutron spectrum:2337300100026 (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 2337300100027 Average fission spectrum cross 2337300100028 section = 113+-7 mb. 2337300100029 (12-MG-24(N,P)11-NA-24,,SIG,,FIS) 2337300100030 Average fission spectrum cross 2337300100031 section = 1.53+-0.09 mb. 2337300100032 (13-AL-27(N,A)11-NA-24,,SIG,,FIS) 2337300100033 Average fission spectrum cross 2337300100034 section = 0.725+-0.045 mb. 2337300100035 ANALYSIS .For the threshold reactions the aver. fis. spectrum 2337300100036 cross section (acs) was determined from the relation 2337300100037 acs = R/F where R is the absolute reaction rate and 2337300100038 F the equivalent fission flux. 2337300100039 R was measured with a calibrated Ge(Li)-detector. 2337300100040 F was determined using the standard threshold 2337300100041 reactions 58-Ni(n,p) , 24-Mg(n,p) and 27-Al(n,alpha). 2337300100042 CORRECTION Because of the thin samples no correction for self 2337300100043 shielding and self absorption is needed. 2337300100044 For the distinction of the fission spectrum of the 2337300100045 irradiation positions from the theoretical fission 2337300100046 spectrum (Watt-spectrum). 2337300100047 ERR-ANALYS (ERR-S) Standard deviation 2337300100048 (DATA-ERR) Absolute total error 2337300100049 include : 2337300100050 * Uncertainties in the half lives and the intensities 2337300100051 of the measured gamma rays. 2337300100052 * Uncertainties in the g-factors. 2337300100053 * Difference of the true fission spectrum from the 2337300100054 theoretical one. 2337300100055 HISTORY (20180710T) M.M. Subents 20625.006, .015, .041 ( data 2337300100056 for incident fission neutron spectrum) were moved in 2337300100057 this Entry. BIB information was updated. 2337300100058 REL-REFs were added. 2337300100059 ENDBIB 57 0 2337300100060 NOCOMMON 0 0 2337300100061 ENDSUBENT 60 0 2337300199999 SUBENT 23373002 20180710 22692337300200001 BIB 6 21 2337300200002 REACTION (13-AL-27(N,P)12-MG-27,,SIG,,FIS) 2337300200003 Average fis. spectrum cross section 2337300200004 SAMPLE Al foils 2337300200005 ANALYSIS Average for 6 measured values - 2337300200006 3.26, 3.63, 3.42 b ( irradiation without Cd filter, 2337300200007 Eeff=4.3 MeV ), 2337300200008 3.08, 3.45, 3.10 b ( irradiation with Cd filter, 2337300200009 spectrum of Et=1.90MeV). 2337300200010 REL-REF (A,,R.Richmond,W,RICHMOND,1959) 2337300200011 3.43 mb relative to U-238(n,f)=304. mb 2337300200012 quoted in REL-REF of R.S.Rochlin 2337300200013 (R,,R.S.Rochlin,J,NUC,17,(1),54,1959) 2337300200014 (A,,J.W.Boldeman,J,JNE/AB,18,417,1964) 2337300200015 2.9+-0.5 mb relative to S-32(n,p)=60. mb 2337300200016 (A,,M.Najzer+,C,70HELSINKI,2,571,1970) 2337300200017 =S,STI/PUB/259,1970 2337300200018 2.9+-0.3 mb relative to Al-27(n,a)=0.61 mb 2337300200019 STATUS (TABLE) Table 1 of J.Radioanal.Chem.,46,159,1978 2337300200020 Table 7/16 of thesis,1976 2337300200021 HISTORY (20180710C) M.M. Subent was moved from 20625.006 , 2337300200022 STATUS, ANALYSIS, ERR-S were added. 2337300200023 ENDBIB 21 0 2337300200024 NOCOMMON 0 0 2337300200025 DATA 4 1 2337300200026 EN-DUMMY DATA DATA-ERR ERR-S 2337300200027 MEV MB MB MB 2337300200028 1.5 3.32 0.38 0.22 2337300200029 ENDDATA 3 0 2337300200030 ENDSUBENT 29 0 2337300299999 SUBENT 23373003 20180710 22692337300300001 BIB 5 25 2337300300002 REACTION (28-NI-60(N,P)27-CO-60,,SIG,,FIS) 2337300300003 Average fis. spectrum cross section 2337300300004 ANALYSIS Average for 6 measured values - 2337300300005 3.97, 4.32, 4.20 b ( irradiation without Cd filter, 2337300300006 Eeff=6.08 MeV ), 2337300300007 3.16, 3.54, 3.62 b ( irradiation with Cd filter, 2337300300008 spectrum of Et=2.08 MeV). 2337300300009 REL-REF (A,,C.E.Mellish+,R,AERE-I/R-2630,1958) 2337300300010 3-7 mb relative to S-32(n,p)=30 mb 2337300300011 (A,,B.L.Robinson+,W,ROBINSON,1959) 2337300300012 <4.5 mb relative to S-32(n,p)= 30mb 2337300300013 quoted in next rel.ref. 2337300300014 (D,,R.S.Rochlin,J,NUC,17,(1),54,1959) 2337300300015 < 2. mb relative to Al-27(n,alpha)= 0.60 mb 2337300300016 (A,,R.W.Durham+,R,AECL-1434,1962) 2337300300017 3.2 mb +- 15% relative to U-238(n,f)= 310 mb 2337300300018 - D,,C.H.Hogg+,C, Proc.Symp. Los Angeles, American 2337300300019 Society for Testing and Materials, page 133, 1963 2337300300020 < 0.5 mb relative to Al-27(n,alpha)= 0.57 mb 2337300300021 (A,,J.R.Hansen+,J,RCA,17,47,1970) 2337300300022 4.4+-1.0 mb relative to Ni-58(n,p)= 105. mb 2337300300023 STATUS (TABLE) Table 1 of J.Radioanal.Chem.,46,159,1978 2337300300024 Table 7/16 of thesis,1976 2337300300025 HISTORY (20180710C) M.M. Subent was moved from 20625.015 , 2337300300026 STATUS, ANALYSIS, ERR-S were added. 2337300300027 ENDBIB 25 0 2337300300028 NOCOMMON 0 0 2337300300029 DATA 4 1 2337300300030 EN-DUMMY DATA DATA-ERR ERR-S 2337300300031 MEV MB MB MB 2337300300032 1.5 3.80 0.62 0.44 2337300300033 ENDDATA 3 0 2337300300034 ENDSUBENT 33 0 2337300399999 SUBENT 23373004 20180710 22692337300400001 BIB 7 17 2337300400002 REACTION (92-U-233(N,2N)92-U-232,,SIG,,FIS) 2337300400003 Average fis. spectrum cross section 2337300400004 SAMPLE U-232 content 1.6E-4 wt.% in U-233 enriched sample 2337300400005 was measured by alpha-spectrometry. 2337300400006 METHOD (CHSEP,ASPEC) Alpha-spectrometry by a surface-barrier 2337300400007 detector and liquid scintillator to define U-232 2337300400008 activity after chemical separation of sample 2337300400009 irradiated with Cd filter in spectrum of Et=5.93 MeV . 2337300400010 ANALYSIS Average of three measured values - 3.64, 3.82, 4.10 b.2337300400011 REL-REF (A,,J.Halperin+,R,ORNL-4306,1968) 2337300400012 3.5 mb relative to Fe-54(n,p)= 65. mb 2337300400013 (A,,K.Kobayashi+,J,NST,10,668,1973) 2337300400014 4.08+-0.30 mb relative to Ni-58(n,p)=102.1 mb 2337300400015 STATUS (TABLE) Table 1 of J.Radioanal.Chem.,46,159,1978 2337300400016 Table 7/16 of thesis,1976 2337300400017 HISTORY (20180710C) M.M. Subent was moved from 20625.041 , 2337300400018 STATUS, ANALYSIS, ERR-S were added. 2337300400019 ENDBIB 17 0 2337300400020 NOCOMMON 0 0 2337300400021 DATA 4 1 2337300400022 EN-DUMMY DATA DATA-ERR ERR-S 2337300400023 MEV MB MB MB 2337300400024 1.5 3.85 0.45 0.23 2337300400025 ENDDATA 3 0 2337300400026 ENDSUBENT 25 0 2337300499999 ENDENTRY 4 0 2337399999999