ENTRY 31742 20140326 31633174200000001 SUBENT 31742001 20140326 31633174200100001 BIB 18 51 3174200100002 TITLE Measurement of effective neutron cross section of the 3174200100003 reaction 98Mo(n,gamma)99Mo in TRR nuclear reactor by 3174200100004 using thermal neutrons 3174200100005 AUTHOR (A.R.Jokar,M.R.Davarpanah,M.Keyvani Ghamsari) 3174200100006 INSTITUTE (3IRNIRN) Nuclear Science and Technology Research 3174200100007 Institute, AEOI, P.O. Box: 143995-1113, Tehran, Iran 3174200100008 REFERENCE (J,ANE,63,653,2014) 3174200100009 #doi:10.1016/j.anucene.2013.08.035 3174200100010 FACILITY (REAC) Tehran research reactor 3174200100011 INC-SOURCE (REAC) 3174200100012 INC-SPECT Thermal and epithermal neutron fluxes were calculated 3174200100013 by using the MCNP Monte Carlo transport code. 3174200100014 Thermal neutron flux: 3174200100015 without Cd (4.11 +/-0.075)x10**13 n/cm2/s 3174200100016 with Cd (0.017 +/-0.0003)x10**13 n/cm2/s 3174200100017 Epithermal neutron flux: 3174200100018 without Cd (0.224 +/-0.001)x10**13 n/cm2/s 3174200100019 with Cd (0.229 +/-0.001)x10**13 n/cm2/s 3174200100020 The index in Westcott's convention = 0.0545 +/- 0.001 3174200100021 DETECTOR (HPGE) HpGe detector with 80% relative efficiency. 3174200100022 The full peak efficiency calibration was performed 3174200100023 using a mixed standard radionuclides solution 3174200100024 containing 152Eu. 3174200100025 METHOD (ACTIV) Samples were irradiated for 15 min. 3174200100026 (CADMB) Samples were irradiated with and without Cd 3174200100027 cover. 3174200100028 SAMPLE (42-MO-98,NAT=0.2439) Natural MoO3 diluted in Au2O3. 3174200100029 Al2O3-4.068%MoO3. Monitor samples diluted Au2O3 and 3174200100030 Co3O4. Al2O3-2.123%Au2O3 and Al2O3-2.854%Co3O4 respect.3174200100031 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,SIG) 3174200100032 ((MONIT2)79-AU-197(N,G)79-AU-198,,RI) 3174200100033 ((MONIT3)27-CO-59(N,G)27-CO-60,,SIG) 3174200100034 ((MONIT4)27-CO-59(N,G)27-CO-60,,RI) 3174200100035 DECAY-MON ((MONIT1)79-AU-198-G,64.68HR,DG,411.8,0.955) 3174200100036 ((MONIT3)27-CO-60-G,5.271YR,DG,1173.,0.9990, 3174200100037 DG,1333.,0.9998) 3174200100038 MONIT-REF ((MONIT1)V1002484,S.F.Mughaghab,R,INDC(NDS)-440,2003) 3174200100039 ((MONIT2)V1002486,S.F.Mughaghab,R,INDC(NDS)-440,2003) 3174200100040 ((MONIT3)V1001216,S.F.Mughaghab,R,INDC(NDS)-440,2003) 3174200100041 ((MONIT4)V1001217,S.F.Mughaghab,R,INDC(NDS)-440,2003) 3174200100042 DECAY-DATA (42-MO-99,65.94HR,DG,739.5,0.1213) 3174200100043 CORRECTION The following corrections ware applied: thermal 3174200100044 neutron selfshielding, epithermal neutron 3174200100045 self-shielding and gamma-ray attenuation. 3174200100046 ERR-ANALYS (ERR-T) Absolute value given. 3174200100047 (ERR-1) Uncertainty in the measurement of the thermal 3174200100048 neutron flux (1.82%). 3174200100049 (ERR-2) Total systematic error in measurement of the 3174200100050 activity of 99Mo (3.4%). 3174200100051 STATUS (TABLE) Data from Table 6 of Ann.Nucl.En. 63,653(2014) 3174200100052 HISTORY (20140326C) VS. 3174200100053 ENDBIB 51 0 3174200100054 COMMON 3 3 3174200100055 KT-K ERR-1 ERR-2 3174200100056 K PER-CENT PER-CENT 3174200100057 300. 1.82 3.4 3174200100058 ENDCOMMON 3 0 3174200100059 ENDSUBENT 58 0 3174200199999 SUBENT 31742002 20140326 31633174200200001 BIB 1 3 3174200200002 REACTION (42-MO-98(N,G)42-MO-99,,SIG,,SPA) 3174200200003 The contribution of the epithermal neutrons 3174200200004 in total neutron activity of 99Mo was 69%. 3174200200005 ENDBIB 3 0 3174200200006 NOCOMMON 0 0 3174200200007 DATA 10 1 3174200200008 DATA ERR-T MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 3174200200009 MONIT3 MONIT3-ERR MONIT4 MONIT4-ERR 3174200200010 B B B B B B 3174200200011 B B B B 3174200200012 0.526 0.02 98.65 0.09 1550. 28. 3174200200013 37.18 0.06 75.9 2.0 3174200200014 ENDDATA 6 0 3174200200015 ENDSUBENT 14 0 3174200299999 ENDENTRY 2 0 3174299999999