ENTRY M1053 20250113 M105300000001 SUBENT M1053001 20250113 20250711 M105300100001 BIB 14 49 M105300100002 TITLE Measurement of flux-weighted average M105300100003 cross-section in the photo-neutron reactions of Nb M105300100004 at the bremsstrahlung end-point energies of 20 and M105300100005 67 MeV. M105300100006 AUTHOR (R.V.Avetisyan,A.G.Barseghyan,Yu.A.Gharibyan, M105300100007 A.V.Gyurjinyan,H.A.Mkrtchyan,A.Yu.Petrosyan, M105300100008 I.A.Kerobyan) M105300100009 REFERENCE (J,NIM/B,557,165557,2024) M105300100010 #doi:10.1016/j.nimb.2024.165557 M105300100011 INSTITUTE (4ARMJER) M105300100012 FACILITY (LINAC,4ARMJER) Electron linear accelerator LUE-75 at M105300100013 the A.I.Alikhanian National Science Laboratory M105300100014 (AANL), Yerevan, Armenia. M105300100015 INC-SOURCE (BRST) Bremsstrahlung with end-point energies 20 and M105300100016 67 MeV. M105300100017 SAMPLE (41-NB-93,NAT=0.999) 150 micron thick niobium target M105300100018 with 2.3 cm x 2.4 cm dimensions. M105300100019 DETECTOR (HPGE) The ORTEC high-purity germanium detector M105300100020 detector. M105300100021 METHOD (GSPEC) M105300100022 ANALYSIS The MAESTRO soft ware package was used for measured M105300100023 spectra processing. M105300100024 The flux-weighted average reaction cross sections M105300100025 were obtained using equation (1) of the article. M105300100026 ERR-ANALYS (ERR-T) M105300100027 The total errors of the experimental data are the M105300100028 quadratic sum of the statistical and systematic M105300100029 errors: M105300100030 (ERR-S) statistical errors are associated with the M105300100031 measurement of the activity of the irradiated M105300100032 material (about 7 %) M105300100033 (ERR-1) systematic errors, photon flux (about 7 %) M105300100034 (ERR-2) systematic errors, irradiation time (2 %) M105300100035 (ERR-3) systematic errors, determination of the M105300100036 detector efficiency (about 2 %). M105300100037 MONITOR (29-CU-65(G,N)29-CU-64,,SIG) M105300100038 The monitor reaction was used to measure the M105300100039 bremsstrahlung flux. M105300100040 The flux-weighted average cross section for M105300100041 65Cu(g,n)64Cu monitor reaction was obtained using M105300100042 formulas (2) and (3) of the article. M105300100043 Two possible gamma lines are available for monitor M105300100044 reaction are 511 keV and 1345.77 keV. M105300100045 CRITIQUE Gamma line energies of monitor reaction should be M105300100046 presented in keV as in Table 1 of article, not in M105300100047 MeV as in the text on page 2 (left column, 11-12 M105300100048 lines from the top). M105300100049 HISTORY (20250113C) Data were compiled at the Russia MSU SINP M105300100050 CDFE by V.Varlamov. M105300100051 ENDBIB 49 0 M105300100052 COMMON 4 3 M105300100053 ERR-S ERR-1 ERR-2 ERR-3 M105300100054 PER-CENT PER-CENT PER-CENT PER-CENT M105300100055 7.0 7.0 2.0 2.0 M105300100056 ENDCOMMON 3 0 M105300100057 ENDSUBENT 56 0 M105300199999 SUBENT M1053002 20250113 20250711 M105300200001 BIB 3 5 M105300200002 REACTION (41-NB-93(G,N)41-NB-92-M,,SIG,,BRA) M105300200003 The flux-weighted average reaction cross sections. M105300200004 DECAY-DATA (41-NB-92-M,10.15D,DG,933.44,0.9915) M105300200005 STATUS (TABLE,,R.V.Avetisyan+,J,NIM/B,557,165557,2024) M105300200006 Data from Table 3. M105300200007 ENDBIB 5 0 M105300200008 NOCOMMON 0 0 M105300200009 DATA 3 2 M105300200010 EN-MAX DATA ERR-T M105300200011 MEV MB MB M105300200012 20. 38.51 4.30 M105300200013 67. 17.07 1.95 M105300200014 ENDDATA 4 0 M105300200015 ENDSUBENT 14 0 M105300299999 SUBENT M1053003 20250113 20250711 M105300300001 BIB 3 6 M105300300002 REACTION (41-NB-93(G,3N)41-NB-90-G,,SIG,,BRA) M105300300003 The flux-weighted average reaction cross sections. M105300300004 DECAY-DATA (41-NB-90-G,14.6HR,DG,141.18,0.668, M105300300005 DG,1129.2,0.0927) M105300300006 STATUS (TABLE,,R.V.Avetisyan+,J,NIM/B,557,165557,2024) M105300300007 Data from Table 3. M105300300008 ENDBIB 6 0 M105300300009 NOCOMMON 0 0 M105300300010 DATA 3 1 M105300300011 EN-MAX DATA ERR-T M105300300012 MEV MB MB M105300300013 67. 2.41 0.20 M105300300014 ENDDATA 3 0 M105300300015 ENDSUBENT 14 0 M105300399999 SUBENT M1053004 20250113 20250711 M105300400001 BIB 3 6 M105300400002 REACTION (41-NB-93(G,4N)41-NB-89-M,,SIG,,BRA) M105300400003 The flux-weighted average reaction cross sections. M105300400004 DECAY-DATA (41-NB-89-M,1.1HR,DG,588.0,0.9557, M105300400005 DG,769.6,0.6270) M105300400006 STATUS (TABLE,,R.V.Avetisyan+,J,NIM/B,557,165557,2024) M105300400007 Data from Table 3. M105300400008 ENDBIB 6 0 M105300400009 NOCOMMON 0 0 M105300400010 DATA 3 1 M105300400011 EN-MAX DATA ERR-T M105300400012 MEV MB MB M105300400013 67. 0.140 0.015 M105300400014 ENDDATA 3 0 M105300400015 ENDSUBENT 14 0 M105300499999 SUBENT M1053005 20250113 20250711 M105300500001 BIB 3 7 M105300500002 REACTION (41-NB-93(G,4N)41-NB-89-G,,SIG,,BRA) M105300500003 The flux-weighted average reaction cross sections. M105300500004 DECAY-DATA (41-NB-89-G,2.03HR,DG,920.0,0.014, M105300500005 DG,1127.2,0.021, M105300500006 DG,1627.2,0.0352) M105300500007 STATUS (TABLE,,R.V.Avetisyan+,J,NIM/B,557,165557,2024) M105300500008 Data from Table 3. M105300500009 ENDBIB 7 0 M105300500010 NOCOMMON 0 0 M105300500011 DATA 3 1 M105300500012 EN-MAX DATA ERR-T M105300500013 MEV MB MB M105300500014 67. 0.540 0.062 M105300500015 ENDDATA 3 0 M105300500016 ENDSUBENT 15 0 M105300599999 ENDENTRY 5 0 M105399999999