ENTRY 22342 20220215 23092234200000001 SUBENT 22342001 20220215 23092234200100001 BIB 15 60 2234200100002 TITLE Measurement of thermal neutron cross section and 2234200100003 resonance integral of the reaction 135-Cs(n,g)136-Cs 2234200100004 AUTHOR (T.Katoh,S.Nakamura,H.Harada,Y.Hatsukawa,N.Shinohara, 2234200100005 K.Hata,K.Kobayashi,S.Motoishi,M.Tanase) 2234200100006 INSTITUTE (2JPNPNC) Katoh, nakamura, harada 2234200100007 (2JPNJAE) hatsukawa, shinohara, hata, kabayashi, 2234200100008 motoishi, tanase 2234200100009 REFERENCE (J,NST,34,431,1997) Experimental details and 2234200100010 final results are given 2234200100011 ((S,INDC(JPN)-179,222,1997)= 2234200100012 (S,JAERI-C-97-005,222,1997)) 2234200100013 proceedings of symposium november 21-22 1996, JAERI, 2234200100014 Japan, published March 1997. Final data are given. 2234200100015 (C,97TRIEST,2,1335,1997) 2234200100016 FACILITY (REAC,2JPNJAE) JRR-3 reactor 2234200100017 METHOD (ACTIV) Activation 2234200100018 DETECTOR (HPGE) Efficiency 90%, energy resolution 2.1 keV FWHM 2234200100019 at 1333 keV gamma energy 2234200100020 MONITOR ((MONIT1)27-CO-59(N,G)27-CO-60,,SIG) 2234200100021 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 2234200100022 cobalt/aluminium and gold/aluminium alloys were 2234200100023 used for monitoring of neutron flux 2234200100024 DECAY-MON (27-CO-60-G,5.271YR,DG,1173.,0.9990, 2234200100025 DG,1332.,0.9998) 2234200100026 (79-AU-198-G,2.696D,DG,412.,0.955) 2234200100027 SAMPLE Cs-Cl solution poured in the quartz tube, 2234200100028 Cs-135/Cs-137 ratio was measured by the quadrupole 2234200100029 mass spectrometer 2234200100030 Cobalt monitor sample is 0.46% Co/Al alloy wire, 2234200100031 0.381 mm diam,99.9313% purity, weights 2.123 and 2234200100032 4.083 mg 2234200100033 Gold monitor sample is 0.112% Au/Al alloy wire, 2234200100034 0.510 mm diam,99.9845% purity, weights 0.518 and 2234200100035 0.506 mg 2234200100036 INC-SPECT Neutron irradiation of targets was performed at the 2234200100037 hydraulic tube facility of JRR-3 reactor. Samples 2234200100038 were irradiated with cadmium shield and without this 2234200100039 shield 2234200100040 DECAY-DATA (55-CS-136-G,12.63D,DG,819.,0.9970, 2234200100041 DG,1048.,0.798, 2234200100042 DG,1235.,0.197) 2234200100043 (55-CS-137,30.174YR,DG,662.,0.860) tracer of Cs-135 2234200100044 ERR-ANALYS (ERR-T) Total error consisting of statistical error 2234200100045 (not given) and several systematic errors - 2234200100046 ERR-1 to ERR-4 2234200100047 (ERR-1) error in the gamma-ray full energy peak 2234200100048 efficiency 2234200100049 (ERR-2) error in the neutron flux measurement 2234200100050 (ERR-3) error in the emission probability per decay 2234200100051 of each gamma-ray 2234200100052 (ERR-4) error in the measurement of the isotopic ratio 2234200100053 of 135-Cs/137-Cs by the quadrupole mass 2234200100054 spectrometer 2234200100055 STATUS (TABLE) Tbl.9 from Nucl.Sci.Tech.,34(1997)431 2234200100056 HISTORY (19970715C) + + Compiled by S. Maev + + 2234200100057 (19980730U) * * new reference added 2234200100058 (20041204A) .bib-info correcred, two subents added 2234200100059 (20220215A) SD:Updated to new date formats,lower case. 2234200100060 Year of the JAERI-C-97-005,222 ref. 2234200100061 updated (1996 -> 1997). 2234200100062 ENDBIB 60 0 2234200100063 COMMON 6 3 2234200100064 MONIT1 MONIT2 ERR-1 ERR-2 ERR-3 ERR-4 2234200100065 B B PER-CENT PER-CENT PER-CENT PER-CENT 2234200100066 37.18 98.65 1.5 1.5 1.0 3.0 2234200100067 ENDCOMMON 3 0 2234200100068 ENDSUBENT 67 0 2234200199999 SUBENT 22342002 20041204 00002234200200001 BIB 1 1 2234200200002 REACTION (55-CS-135(N,G)55-CS-136,,SIG) 2234200200003 ENDBIB 1 0 2234200200004 NOCOMMON 0 0 2234200200005 DATA 3 1 2234200200006 EN DATA ERR-T 2234200200007 EV B B 2234200200008 2.53E-02 8.300E+00 3.000E-01 2234200200009 ENDDATA 3 0 2234200200010 ENDSUBENT 9 0 2234200299999 SUBENT 22342003 20041204 00002234200300001 BIB 1 1 2234200300002 REACTION (55-CS-135(N,G)55-CS-136,,RI,,RNV) 2234200300003 ENDBIB 1 0 2234200300004 NOCOMMON 0 0 2234200300005 DATA 3 1 2234200300006 EN-MIN DATA ERR-T 2234200300007 EV B B 2234200300008 5.5 E-01 3.4300E+01 2.600E+00 2234200300009 ENDDATA 3 0 2234200300010 ENDSUBENT 9 0 2234200399999 SUBENT 22342004 20041204 00002234200400001 BIB 2 3 2234200400002 REACTION (55-CS-135(N,G)55-CS-136,,RI,,,DERIV) 2234200400003 STATUS (DEP,22342002) 2234200400004 (DEP,22342003) 2234200400005 ENDBIB 3 0 2234200400006 NOCOMMON 0 0 2234200400007 DATA 3 1 2234200400008 EN-MIN DATA ERR-T 2234200400009 EV B B 2234200400010 5.5 E-01 3.790E+01 2.700E+00 2234200400011 ENDDATA 3 0 2234200400012 ENDSUBENT 11 0 2234200499999 ENDENTRY 4 0 2234299999999