ENTRY 31509 20211005 32023150900000001 SUBENT 31509001 20211005 32023150900100001 BIB 14 46 3150900100002 INSTITUTE (3POLITJ) 3150900100003 REFERENCE (J,ANE,26,83,1999) 3150900100004 AUTHOR (J.Janczyszyn,G.Domanska,W.Pohorecki) 3150900100005 TITLE Measurement of cross section for 24Na production from 3150900100006 magnesium isotopes by 13.5-18.0 MeV neutrons 3150900100007 FACILITY (VDG,3POLIPJ) 3 MV Van de Graff of 25 micro-Ampere 3150900100008 deuteron beam served as neutron source. 3150900100009 INC-SOURCE (D-T) The T-target in the form of titanium tritide was 3150900100010 about 1.12 mg/cm**2 thick. Two deuteron energies were 3150900100011 applied: 1.8 and 2.0 MeV 3150900100012 INC-SPECT Monoenergetic neutrons 3150900100013 SAMPLE Enriched samples of MgO (Mg-25: 96.4+-0.3%, 3150900100014 Mg-26: 97.1+-0.2%) and 99.99% Al foil were used. 3150900100015 The weight of magnesium samples was around 70-80 mg 3150900100016 and of Al foils was around 170 mg. 3150900100017 METHOD (ACTIV) 3150900100018 Powder samples of MgO were placed in perspex containers3150900100019 around which the Al standard-monitor foil was wrapped. 3150900100020 The weight of magnesium samples and Al foils was chosen3150900100021 to achieve approximately equal dead-time and pile-up 3150900100022 effects, during counting. 3150900100023 After irradiation and ca. 5h decay the samples were 3150900100024 counted with NaI(Tl) detector for 2000-4000 s. Since 3150900100025 the 24Na-lines only were observed, the integral 3150900100026 counting was performed within the gamma-energy range 3150900100027 from 0.4-3.0 MeV. 3150900100028 MgO sample and Al foil were activated simultaneously 3150900100029 in the same position of the sample holder, were counted3150900100030 directly one after another to minimise instrumental 3150900100031 errors. 3150900100032 DETECTOR (NAICR) 7.5*7.5 cm Na-I(Tl) detector 3150900100033 DECAY-DATA (11-NA-24,14.960HR,DG,1368.,,DG,2754.) 3150900100034 Uncertainty of half-life is 0.006 hr. 3150900100035 STATUS (TABLE) Data taken from J.Ann.Nucl.Energy, 3150900100036 vol.26(1999), p.88, Table 4. 3150900100037 COMMENT Absolute cross section data for the 3150900100038 reaction (12-MG-24(N,P)11-NA-24,,SIG) described 3150900100039 in J.Ann.Nucl.Energy, Vol.15(1988) Pag.155 3150900100040 were recalculated by authors with improved method. 3150900100041 These data from J.Ann.Nucl.Energy, Vol.26 (1999), 3150900100042 Pag.88 Table 3 are given in EXFOR.30799 3150900100043 HISTORY (20010129C) VZ 3150900100044 (20010620U) OS. Added tautologies, moved MONITOR to 3150900100045 subentries 3150900100046 (20211004A) VS. SF3=X in 002-003; ERR-T -> DATA-ERR in 3150900100047 002; ERR-ANALYS moved from 001 to 002. 3150900100048 ENDBIB 46 0 3150900100049 NOCOMMON 0 0 3150900100050 ENDSUBENT 49 0 3150900199999 SUBENT 31509002 20211005 32023150900200001 BIB 5 16 3150900200002 REACTION 1((12-MG-25(N,X)11-NA-24,,SIG)/ 3150900200003 (13-AL-27(N,A)11-NA-24,,SIG)) 3150900200004 2(12-MG-25(N,X)11-NA-24,,SIG) 3150900200005 MONITOR 2(13-AL-27(N,A)11-NA-24,,SIG) 3150900200006 Values were obtained by recalculation of nuclear data 3150900200007 standards for nuclear measurements, p.59, IAEA 3150900200008 Technical Report Series No.227, Vienna. of H.Vonach 3150900200009 (1983). 3150900200010 MONIT-REF (,H.Vonach,R,STI/DOC/10-227,59,1983) 3150900200011 ERR-ANALYS (DATA-ERR) 3150900200012 - Statistical 3150900200013 - Systematic 3150900200014 Most of the systematic errors were eliminated in 3150900200015 the applied procedure. 3150900200016 HISTORY (20211004A) VS. SF3=X: Memos CP-D/0999 and CP-D/0954; 3150900200017 ERR-T -> DATA-ERR; ERR-ANALYS moved from 001. 3150900200018 ENDBIB 16 0 3150900200019 NOCOMMON 0 0 3150900200020 DATA 8 10 3150900200021 EN EN-RSL MONIT MONIT-ERR DATA 1DATA-ERR 3150900200022 DATA 2DATA-ERR 2 3150900200023 MEV MEV MB MB NO-DIM NO-DIM 3150900200024 MB MB 3150900200025 13.39 0.64 124.5 1.0 0.072 0.006 3150900200026 9.0 0.8 3150900200027 13.40 0.67 124.2 1.0 0.103 0.004 3150900200028 12.8 0.5 3150900200029 14.74 0.82 112.5 0.7 0.257 0.005 3150900200030 28.9 0.6 3150900200031 14.83 0.87 111.3 0.7 0.320 0.021 3150900200032 35.6 2.3 3150900200033 16.27 0.76 89.2 1.7 0.611 0.080 3150900200034 54.5 7.2 3150900200035 16.43 0.80 86.4 1.7 0.704 0.010 3150900200036 60.8 1.5 3150900200037 17.42 0.44 68.8 2.0 0.903 0.027 3150900200038 62.2 2.6 3150900200039 17.66 0.48 65.6 2.1 1.093 0.029 3150900200040 71.3 3.0 3150900200041 17.86 0.08 62.9 2.1 1.049 0.012 3150900200042 66.0 2.3 3150900200043 18.12 0.08 59.9 2.1 1.296 0.068 3150900200044 77.6 4.9 3150900200045 ENDDATA 24 0 3150900200046 ENDSUBENT 45 0 3150900299999 SUBENT 31509003 20211005 32023150900300001 BIB 4 8 3150900300002 REACTION (12-MG-26(N,X)11-NA-24,,SIG) 3150900300003 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3150900300004 Values were obtained by recalculation of nuclear data 3150900300005 standards for nuclear measurements, p.59, IAEA 3150900300006 Technical Report Series No.227, Vienna. of H.Vonach 3150900300007 (1983). 3150900300008 MONIT-REF (,H.Vonach,R,STI/DOC/10-227,59,1983) 3150900300009 HISTORY (20211004A) VS. SF3=X: Memos CP-D/0999 and CP-D/0954. 3150900300010 ENDBIB 8 0 3150900300011 NOCOMMON 0 0 3150900300012 DATA 5 5 3150900300013 EN EN-RSL MONIT MONIT-ERR DATA-MAX 3150900300014 MEV MEV MB MB MB 3150900300015 14.83 0.87 111.3 0.7 9. 3150900300016 16.43 0.80 86.4 1.7 4.5 3150900300017 17.66 0.48 65.6 2.1 3. 3150900300018 17.86 0.08 62.9 2.1 14. 3150900300019 18.12 0.08 59.9 2.1 4.1 3150900300020 ENDDATA 7 0 3150900300021 ENDSUBENT 20 0 3150900399999 ENDENTRY 3 0 3150999999999