ENTRY 14520 20190117 14481452000000001 SUBENT 14520001 20190117 14481452000100001 BIB 12 40 1452000100002 TITLE The surprisingly large neutron capture cross-section 1452000100003 of 88Zr 1452000100004 AUTHOR (J.A.Shusterman,N.D.Scielzo,K.J.Thomas,E.B.Norman, 1452000100005 S.E.Lapi,C.S.Loveless,N.J.Peters,J.D.Robertson, 1452000100006 D.A.Shaughnessy,A.P.Tonchev) 1452000100007 INSTITUTE (1USALRL,1USAUCX,1USAUAL,1USAMIS) 1452000100008 (1USAUSA) City University of New York,New York 1452000100009 REFERENCE (J,NAT,565,328,2019) 1452000100010 FACILITY (REAC,1USAMIS) Neutron irradiations were performed 1452000100011 using thermal-neutron flux in the graphite reflector 1452000100012 of the University of Missouri Research Reactor (MURR) 1452000100013 SAMPLE (40-ZR-88,ENR=0.999) The 88Zr target material was 1452000100014 produced via the 89Y(p,2n)88Zr reaction using a 1452000100015 proton beam from the University of Alabama Cyclotron 1452000100016 Facility at Birmingham.88Zr was chemically purified 1452000100017 using anion-exchange chromatography and assayed before 1452000100018 encapsulation as a salt residue in high-purity quartz 1452000100019 tubes. The 37-kBq 88Zr samples and accompanying quartz 1452000100020 encapsulated natural-metal foils (Fe, Zr, Mo and Y), 1452000100021 which served as flux monitors, 1452000100022 Each target contained 40.7 - 44.4 kBq of 88Zr at the 1452000100023 beginning of irradiation 1452000100024 DECAY-DATA (40-ZR-88,83.4D,DG,392.87,0.9721) 1452000100025 (40-ZR-89-G,3.267D,DG,909.15,0.9904) 1452000100026 DETECTOR (HPGE) High-purity germanium detectors were used to 1452000100027 measure induced activity in reaction products. 1452000100028 MONITOR (26-FE-58(N,G)26-FE-59,,SIG) 1452000100029 (40-ZR-90(N,2N)40-ZR-89,,SIG) 1452000100030 (40-ZR-94(N,G)40-ZR-95,,SIG) 1452000100031 (40-ZR-96(N,G)40-ZR-97,,SIG) 1452000100032 (42-MO-98(N,G)42-MO-99,,SIG) 1452000100033 Reactions (n,g) were used to determine neutron flux 1452000100034 in thermal and resonance regions, (n,2n) reaction was 1452000100035 used to determine the neutron flux above 12.5 MeV 1452000100036 INC-SOURCE The targets and monitors were irradiated simultaneously1452000100037 in the graphite reflector at MURR 1452000100038 INC-SPECT Average thermal neutron flux 7.1E+13 n/cm2/s 1452000100039 Resonance region neutron flux 2.7E+12 n/cm2/s 1452000100040 neutron flux above 12.5 Mev 4.5E+9 n/cm2/s 1452000100041 HISTORY (20190117C) Compiled by S.H. 1452000100042 ENDBIB 40 0 1452000100043 NOCOMMON 0 0 1452000100044 ENDSUBENT 43 0 1452000199999 SUBENT 14520002 20190117 14481452000200001 BIB 6 25 1452000200002 REACTION (40-ZR-88(N,G)40-ZR-89,,SIG,,SPA) 1452000200003 STATUS (TABLE) Data taken from text p.329 of the reference 1452000200004 (SUPPL,14520004) Neutron source spectrum 1452000200005 ANALYSIS The neutron capture cross-section was determined from 1452000200006 the dependence of the final-to-initial atom ratios on 1452000200007 the neutron fluence. 1452000200008 ERR-ANALYS (ERR-1,0.2,11.) Systematic uncertainty in monitor mass 1452000200009 (ERR-2,0.02,10.) Systematic uncertainty in irradiation 1452000200010 time 1452000200011 (ERR-3) Systematic uncertainty in point source HPGe 1452000200012 efficiency used for monitor foils 1452000200013 (ERR-4,0.,2.) Statistical uncertainty in neutron flux 1452000200014 (ERR-5) Systematic uncertainty in reference cross 1452000200015 section data 1452000200016 (ERR-6) Systematic uncertainty in sample geometry 1452000200017 (ERR-7) Systematic uncertainty in point source HPGe 1452000200018 calibration used for sample foils 1452000200019 (ERR-T) Total uncertainty 1452000200020 METHOD (ACTIV) Activation method was used. Irradiation times 1452000200021 varied between 0.08 and 50.15 hours. Cross section was 1452000200022 measured by determining the quantities of 88Zr and of 1452000200023 the reaction product 89Zr using gamma-ray spectroscopy 1452000200024 CORRECTION The Zr populations have been corrected for decay 1452000200025 between the beginning of irradiation and the 1452000200026 measurements performed after irradiation. 1452000200027 ENDBIB 25 0 1452000200028 COMMON 5 3 1452000200029 EN-DUMMY ERR-3 ERR-5 ERR-6 ERR-7 1452000200030 EV PER-CENT PER-CENT PER-CENT PER-CENT 1452000200031 0.0253 1. 7. 6. 1. 1452000200032 ENDCOMMON 3 0 1452000200033 DATA 2 1 1452000200034 DATA ERR-T 1452000200035 B B 1452000200036 8.61E+5 0.69E+5 1452000200037 ENDDATA 3 0 1452000200038 ENDSUBENT 37 0 1452000299999 SUBENT 14520003 20190117 14481452000300001 BIB 3 7 1452000300002 REACTION (40-ZR-89(N,G)40-ZR-90,,SIG,,SPA) 1452000300003 STATUS (TABLE) Data taken from text p. 329 of the reference 1452000300004 (SUPPL,14520004) Neutron source spectrum 1452000300005 ANALYSIS Raction 89Zr(n,g)90Zr could affect the amount of 89Zr 1452000300006 observed. Therefore it was included in the analysis of 1452000300007 data, shown in fig.2 of the reference. Existing data 1452000300008 constrains this cross section to be less than 1.2E+4b. 1452000300009 ENDBIB 7 0 1452000300010 NOCOMMON 0 0 1452000300011 DATA 2 1 1452000300012 EN-DUMMY DATA-MAX 1452000300013 EV B 1452000300014 0.0253 1.2E+4 1452000300015 ENDDATA 3 0 1452000300016 ENDSUBENT 15 0 1452000399999 SUBENT 14520004 20190117 14481452000400001 BIB 1 120 1452000400002 SUPPL-INF (INCSP) Neutron flux calculated by MCNP5 received from 1452000400003 the authors via J.-C.Sublet (26 April 2019). 1452000400004 See also Extended Data Fig.1 of Nature 565(2019)328. 1452000400005 ---------------------------------------- 1452000400006 Grp. Emin Emax neutrons/grp 1452000400007 (eV) (eV) (arb. unit) 1452000400008 ----------------------------------------- 1452000400009 112 1.0500E-09 3.5700E-09 5.03413E+10 1452000400010 111 3.5700E-09 6.4500E-09 5.76347E+11 1452000400011 110 6.4500E-09 8.3700E-09 1.23049E+12 1452000400012 109 8.3700E-09 1.4500E-08 1.30120E+12 1452000400013 108 1.4500E-08 2.8600E-08 5.83710E+12 1452000400014 107 2.8600E-08 3.5000E-08 1.60857E+13 1452000400015 106 3.5000E-08 4.4000E-08 7.43041E+12 1452000400016 105 4.4000E-08 5.5600E-08 1.00368E+13 1452000400017 104 5.5600E-08 6.7500E-08 1.07361E+13 1452000400018 103 6.7500E-08 7.3200E-08 9.20115E+12 1452000400019 102 7.3200E-08 8.1800E-08 3.79796E+12 1452000400020 101 8.1800E-08 8.6700E-08 4.33632E+12 1452000400021 100 8.6700E-08 9.1900E-08 2.20873E+12 1452000400022 99 9.1900E-08 9.8200E-08 2.16471E+12 1452000400023 98 9.8200E-08 1.0500E-07 2.15300E+12 1452000400024 97 1.0500E-07 1.7100E-07 1.92642E+12 1452000400025 96 1.7100E-07 2.3700E-07 8.90221E+12 1452000400026 95 2.3700E-07 2.8000E-07 2.26335E+12 1452000400027 94 2.8000E-07 3.1500E-07 9.59063E+11 1452000400028 93 3.1500E-07 3.6700E-07 5.14728E+11 1452000400029 92 3.6700E-07 4.4500E-07 6.27327E+11 1452000400030 91 4.4500E-07 5.4500E-07 7.27987E+11 1452000400031 90 5.4500E-07 6.3200E-07 7.81512E+11 1452000400032 89 6.3200E-07 7.3700E-07 5.09239E+11 1452000400033 88 7.3700E-07 8.4300E-07 5.76464E+11 1452000400034 87 8.4300E-07 9.4500E-07 4.68347E+11 1452000400035 86 9.4500E-07 1.1500E-06 4.00300E+11 1452000400036 85 1.1500E-06 2.2500E-06 5.83725E+11 1452000400037 84 2.2500E-06 3.5600E-06 2.16899E+12 1452000400038 83 3.5600E-06 4.4500E-06 1.58932E+12 1452000400039 82 4.4500E-06 5.3600E-06 6.40500E+11 1452000400040 81 5.3600E-06 6.5700E-06 6.52475E+11 1452000400041 80 6.5700E-06 7.3200E-06 5.54618E+11 1452000400042 79 7.3200E-06 8.4500E-06 3.28592E+11 1452000400043 78 8.4500E-06 9.4000E-06 4.25668E+11 1452000400044 77 9.4000E-06 1.2700E-05 4.01512E+11 1452000400045 76 1.2700E-05 2.1500E-05 1.04863E+12 1452000400046 75 2.1500E-05 2.9300E-05 1.60545E+12 1452000400047 74 2.9300E-05 3.5500E-05 8.65673E+11 1452000400048 73 3.5500E-05 4.7800E-05 5.56862E+11 1452000400049 72 4.7800E-05 6.1800E-05 9.55838E+11 1452000400050 71 6.1800E-05 8.2500E-05 8.48269E+11 1452000400051 70 8.2500E-05 1.2800E-04 8.43124E+11 1452000400052 69 1.2800E-04 2.4500E-04 1.41210E+12 1452000400053 68 2.4500E-04 3.3400E-04 1.76967E+12 1452000400054 67 3.3400E-04 4.7100E-04 7.88340E+11 1452000400055 66 4.7100E-04 5.5600E-04 9.11270E+11 1452000400056 65 5.5600E-04 6.7300E-04 4.08686E+11 1452000400057 64 6.7300E-04 7.3500E-04 6.01629E+11 1452000400058 63 7.3500E-04 8.6200E-04 2.82397E+11 1452000400059 62 8.6200E-04 9.6700E-04 3.99282E+11 1452000400060 61 9.6700E-04 1.0200E-03 3.06489E+11 1452000400061 60 1.0200E-03 2.4700E-03 1.50214E+11 1452000400062 59 2.4700E-03 3.2300E-03 2.30146E+12 1452000400063 58 3.2300E-03 4.9300E-03 7.17883E+11 1452000400064 57 4.9300E-03 5.5200E-03 1.13188E+12 1452000400065 56 5.5200E-03 6.9200E-03 3.39976E+11 1452000400066 55 6.9200E-03 7.5200E-03 5.47049E+11 1452000400067 54 7.5200E-03 8.3200E-03 1.98027E+11 1452000400068 53 8.3200E-03 9.0500E-03 2.45045E+11 1452000400069 52 9.0500E-03 1.1100E-02 2.28908E+11 1452000400070 51 1.1100E-02 1.8500E-02 5.22493E+11 1452000400071 50 1.8500E-02 2.3000E-02 1.27809E+12 1452000400072 49 2.3000E-02 2.5100E-02 6.40525E+11 1452000400073 48 2.5100E-02 2.8900E-02 1.91523E+11 1452000400074 47 2.8900E-02 3.6400E-02 3.83136E+11 1452000400075 46 3.6400E-02 4.6100E-02 5.69238E+11 1452000400076 45 4.6100E-02 5.4100E-02 5.04068E+11 1452000400077 44 5.4100E-02 8.9200E-02 4.60764E+11 1452000400078 43 8.9200E-02 1.4700E-01 1.55042E+12 1452000400079 42 1.4700E-01 2.4000E-01 1.69961E+12 1452000400080 41 2.4000E-01 3.3300E-01 1.65599E+12 1452000400081 40 3.3300E-01 4.3300E-01 1.57835E+12 1452000400082 39 4.3300E-01 5.5300E-01 1.25471E+12 1452000400083 38 5.5300E-01 6.7500E-01 1.21447E+12 1452000400084 37 6.7500E-01 7.8200E-01 9.43910E+11 1452000400085 36 7.8200E-01 9.1200E-01 9.99520E+11 1452000400086 35 9.1200E-01 1.1800E+00 8.34041E+11 1452000400087 34 1.1800E+00 1.5000E+00 1.40457E+12 1452000400088 33 1.5000E+00 1.7900E+00 1.46955E+12 1452000400089 32 1.7900E+00 2.0800E+00 1.17416E+12 1452000400090 31 2.0800E+00 2.2900E+00 7.53985E+11 1452000400091 30 2.2900E+00 2.3600E+00 4.15752E+11 1452000400092 29 2.3600E+00 2.4200E+00 1.64897E+11 1452000400093 28 2.4200E+00 2.6000E+00 9.73661E+10 1452000400094 27 2.6000E+00 2.8700E+00 2.94202E+11 1452000400095 26 2.8700E+00 3.5300E+00 2.04239E+11 1452000400096 25 3.5300E+00 5.4100E+00 4.59222E+11 1452000400097 24 5.4100E+00 6.7200E+00 7.20303E+11 1452000400098 23 6.7200E+00 7.5500E+00 1.81380E+11 1452000400099 22 7.5500E+00 8.2700E+00 6.78916E+10 1452000400100 21 8.2700E+00 9.6900E+00 3.78223E+10 1452000400101 20 9.6900E+00 1.0000E+01 3.21560E+10 1452000400102 19 1.0000E+01 1.0500E+01 0.00000E+00 1452000400103 18 1.0500E+01 1.0900E+01 1.44141E+10 1452000400104 17 1.0900E+01 1.1300E+01 6.31441E+09 1452000400105 16 1.1300E+01 1.1700E+01 0.00000E+00 1452000400106 15 1.1700E+01 1.2100E+01 0.00000E+00 1452000400107 14 1.2100E+01 1.2600E+01 0.00000E+00 1452000400108 13 1.2600E+01 1.2900E+01 0.00000E+00 1452000400109 12 1.2900E+01 1.3300E+01 0.00000E+00 1452000400110 11 1.3300E+01 1.3800E+01 0.00000E+00 1452000400111 10 1.3800E+01 1.4300E+01 0.00000E+00 1452000400112 9 1.4300E+01 1.4900E+01 0.00000E+00 1452000400113 8 1.4900E+01 1.5400E+01 0.00000E+00 1452000400114 7 1.5400E+01 1.5800E+01 0.00000E+00 1452000400115 6 1.5800E+01 1.6500E+01 0.00000E+00 1452000400116 5 1.6500E+01 1.7000E+01 0.00000E+00 1452000400117 4 1.7000E+01 1.7700E+01 0.00000E+00 1452000400118 3 1.7700E+01 1.8400E+01 0.00000E+00 1452000400119 2 1.8400E+01 1.9300E+01 0.00000E+00 1452000400120 1 1.9300E+01 2.0000E+01 0.00000E+00 1452000400121 ---------------------------------------- 1452000400122 ENDBIB 120 0 1452000400123 NOCOMMON 0 0 1452000400124 NODATA 0 0 1452000400125 ENDSUBENT 124 0 1452000499999 ENDENTRY 4 0 1452099999999