ENTRY 23390 20180411 22692339000000001 SUBENT 23390001 20180411 22692339000100001 BIB 14 66 2339000100002 TITLE Determination of integral fast fission cross sections 2339000100003 (n,f) of 238U, 237Np, and 242Pu in a directed fission 2339000100004 neutron beam at FRM II, Garching 2339000100005 AUTHOR (A.Hable,C.Ramsl, E.Jericha,H.Boeck, T.H.Randriamalala,2339000100006 M.Rossbach) 2339000100007 INSTITUTE (2AUSTHV) A.Hable,C.Ramsl,E.Jericha,H.Boeck 2339000100008 (2GERJUL) T.H.Randriamalala,M.Rossbach 2339000100009 REFERENCE (J,JRN,314,1471,2017) 2339000100010 #doi:10.1007/s10967-017-5512-7 2339000100011 REL-REF (N,,T.H.Randriamalala+,J,NIM/A,806,370,2016) 2339000100012 Neutron flux calculation details. 2339000100013 FACILITY (REAC,2GERJUL)FRM II Research Reactor. 2339000100014 INC-SOURCE (REAC) Fission neutrons from 93% enriched U-235 2339000100015 converter within the D(2)O moderator tank. 2339000100016 MedApp station of FRM II. 2339000100017 INC-SPECT 1.008*10**8 neutrons/cm2/sec . 2339000100018 Fast neutron flux was determined by the metal foil 2339000100019 activation method - for Al,Ti,Fe,Co,Ni,Cu,Au. 2339000100020 Energy distribution is given on Fig.2 of JRN,314,1471 2339000100021 SAMPLE - Depleted U-238 sample, diameter 10 mm, thickness 2339000100022 0.3 mm, packed in teflon foil, positioned at 30 deg 2339000100023 angle, irradiated 12 hr , measured several times for 2339000100024 10 min and 1 hr. 2339000100025 Isotopic composition, % : 2339000100026 U-234 - (7.403+-0.018)*10**-4 2339000100027 U-235 - 0.20039+-0.00012 2339000100028 U-236 - (3.1876+-0.0083)*10**-3 2339000100029 U-238 - 99.79568+-0.00012 2339000100030 - NpO(2) powder, Np-237 isotopic abundance 99.5+-0.1 %,2339000100031 other Np isotopes < 0.7 %. Impurities < 0.1 % . 2339000100032 Pressed to a pellet of 0.2 mm thickness, 3 mm diameter,2339000100033 imbedded in 40 mm x 40 mm x 0.2 mm quarz blades. 2339000100034 Mass of sample - 3.3399+-0.0018 mg corresponds to 2339000100035 (74.38+-0.05)*10**17 Np-237 atoms. 2339000100036 - 242PuO(2) powder, prepared in the same way as Np 2339000100037 sample. 2339000100038 Isotopic composition, % ( as given by ORNL, 1980 yr): 2339000100039 Pu-238 - 0.004 , Pu-239 - 0.005 , Pu-240 - 0.022 , 2339000100040 Pu-241 - 0.035 , Pu-242 - 99.93 %, Pu-244 - 0.022 . 2339000100041 Decay during 37 years was then taken into account and 2339000100042 considered to be very low. 2339000100043 Sample mass 9.3034+-0.0052 mg corresponds 2339000100044 (204.29+-0.12)*10**17 Pu-242 atoms. 2339000100045 DECAY-DATA (92-U-234,2.457E+5YR) (2.457+-0.003)*10**5 yr 2339000100046 (92-U-235,7.038E+8YR) (7.038+-0.005)*10**8 yr 2339000100047 (92-U-236,2.37E+7YR) (2.37+-0.02)*10**7 yr 2339000100048 (92-U-238,4.468E+9YR) (4.468+-0.3)*10**7 yr 2339000100049 (94-PU-238,87.74YR) 87.74+-0.03 yr 2339000100050 (94-PU-239,24100.YR) 24100.+-11. yr 2339000100051 (94-PU-240,6564.YR) 6564.+-7. yr 2339000100052 (94-PU-241,14.33YR) 14.33+-4. yr 2339000100053 (94-PU-242,373000.YR) 373000.+-3000. yr 2339000100054 (94-PU-244,8.12E+7YR) (8.12+-0.03)*10**7 yr 2339000100055 DETECTOR (GE) To measure gammas from activated samples. 2339000100056 CORRECTION For background. 2339000100057 For self-shiending in sample. 2339000100058 ANALYSIS CS was calculated by formula (3) using : 2339000100059 fission yields values calculated by weighting the 2339000100060 cumulative fission yields of JEFF-3.1 at 400 keV and 2339000100061 15 MeV energies; 2339000100062 measured neutron flux, 2339000100063 measured activities of sample, 2339000100064 number of atomsin sample, 2339000100065 decay constants. 2339000100066 HL used were taken from JEFF-3.1 . 2339000100067 HISTORY (20180411C) M.M. 2339000100068 ENDBIB 66 0 2339000100069 NOCOMMON 0 0 2339000100070 ENDSUBENT 69 0 2339000199999 SUBENT 23390002 20180411 22692339000200001 BIB 5 32 2339000200002 REACTION (92-U-238(N,F),,SIG,,SPA) 2339000200003 ANALYSIS Weighted mean cumulative fission yields used in 2339000200004 analysis : 2339000200005 Fis.product Half-life Yield, % 2339000200006 103Ru 39.26 +- 0.02 day 6.03 +- 0.01 2339000200007 140Ba 12.765 +- 0.015 day 5.97 +- 0.09 2339000200008 132Te 3.204 +- 0.013 day 4.76 +- 0.18 2339000200009 99Mo 2.7475 +- 0.0004day 6.18 +- 0.1 2339000200010 143Ce 1.379 +- 0.002 da 4.68 +- 0.12 2339000200011 133J 20.8 +- 0.1 hr 6.71 +- 0.23 2339000200012 91Sr 9.63 +- 0.05 hr 4.16 +- 0.14 2339000200013 135J 6.57 +- 0.02 hr 6.42 +- 0.27 2339000200014 92Sr 2.594 +- 0.006 hr 4.37 +- 0.17 2339000200015 139Ba 1.384 +- 0.004 hr 5.9 +- 0.4 2339000200016 134Te 41.8 +- 0.8 mim 6.6 +- 0.7 2339000200017 94Y 18.7 +- 0.1 min 4.93 +- 0.25 2339000200018 104Tc 18.3 +- 0.3 min 4.9 +- 0.9 2339000200019 141Ba 18.27 +- 0.07 min 5.9 +- 0.5 2339000200020 101Mo 14.61 +- 0.03 min 6.43 +- 0.29 2339000200021 143La 14.14 +- 0.16 min 4.68 +- 0.12 2339000200022 138Xe 14.08 +- 0.08 min 5.99 +- 0.23 2339000200023 142Ba 10.6 +- 0.2 min 4.89 +- 0.27 2339000200024 95Y 10.3 +- 0.1 min 5.19 +- 0.09 2339000200025 93Sr 7.42 +- 0.02 min 5.38 +- 0.27 2339000200026 ADD-RES (COMP) Measured CS are compared by spectum average CS 2339000200027 determined by formula (4) using data of evaluated data 2339000200028 libraries: 2339000200029 ENDF - 336.2b ( max. 351.8 b, min. 318.9 b ) 2339000200030 JEFF - 346.6b ( max. 365.7 b, min. 323.5 b ) 2339000200031 JENDL - 335.5b ( max. 349.6 b, min. 319.4 b ) 2339000200032 ERR-ANALYS (DATA-ERR) Type of error is not explained in article 2339000200033 STATUS (TABLE) Table 5 of J.Radioanal.Nucl.Chem.,314,1471,20172339000200034 ENDBIB 32 0 2339000200035 NOCOMMON 0 0 2339000200036 DATA 4 1 2339000200037 EN EN-ERR DATA DATA-ERR 2339000200038 MEV MEV B B 2339000200039 2.12 0.08 0.38 0.04 2339000200040 ENDDATA 3 0 2339000200041 ENDSUBENT 40 0 2339000299999 SUBENT 23390003 20180411 22692339000300001 BIB 4 9 2339000300002 REACTION (93-NP-237(N,F),,SIG,,SPA) 2339000300003 ADD-RES (COMP) Measured CS are compared by spectum average CS 2339000300004 determined by formula (4) using data of evaluated data 2339000300005 libraries: 2339000300006 ENDF - 1.389b ( max. 1.420 b, min. 1.372 b ) 2339000300007 JEFF - 1.365b ( max. 1.380 b, min. 1.350 b ) 2339000300008 JENDL - 1.380b ( max. 1.404 b, min. 1.368 b) 2339000300009 ERR-ANALYS (DATA-ERR) Type of error is not explained in article 2339000300010 STATUS (TABLE) Table 5 of J.Radioanal.Nucl.Chem.,314,1471,20172339000300011 ENDBIB 9 0 2339000300012 NOCOMMON 0 0 2339000300013 DATA 4 1 2339000300014 EN EN-ERR DATA DATA-ERR 2339000300015 MEV MEV B B 2339000300016 2.12 0.08 3.17 0.25 2339000300017 ENDDATA 3 0 2339000300018 ENDSUBENT 17 0 2339000399999 SUBENT 23390004 20180411 22692339000400001 BIB 4 9 2339000400002 REACTION (94-PU-242(N,F),,SIG,,SPA) 2339000400003 ADD-RES (COMP) Measured CS are compared by spectum average CS 2339000400004 determined by formula (4) using data of evaluated data 2339000400005 libraries: 2339000400006 ENDF - 1.185b ( max. 1.214 b, min. 1.171 b ) 2339000400007 JEFF - 1.203b ( max. 1.250 b, min. 1.177 b ) 2339000400008 JENDL - 1.186b ( max. 1.219 b, min. 1.172 b) 2339000400009 ERR-ANALYS (DATA-ERR) Type of error is not explained in article 2339000400010 STATUS (TABLE) Table 5 of J.Radioanal.Nucl.Chem.,314,1471,20172339000400011 ENDBIB 9 0 2339000400012 NOCOMMON 0 0 2339000400013 DATA 4 1 2339000400014 EN EN-ERR DATA DATA-ERR 2339000400015 MEV MEV B B 2339000400016 2.12 0.08 2.15 0.3 2339000400017 ENDDATA 3 0 2339000400018 ENDSUBENT 17 0 2339000499999 ENDENTRY 4 0 2339099999999