ENTRY 21738 20200807 22902173800000001 SUBENT 21738001 20200807 22902173800100001 BIB 18 68 2173800100002 TITLE Gamma competition in the decay of unbound states 2173800100003 in Fe-56 produced by the Fe-56(n,inl) reaction 2173800100004 with 14 MeV neutrons 2173800100005 AUTHOR (G.Stengl,M.Uhl,H.Vonach) 2173800100006 REFERENCE (J,NP/A,290,109,1977) 2173800100007 (J,OSA,114,117,1977) abstract. 2173800100008 INSTITUTE (2AUSIRK) 2173800100009 FACILITY (NGEN,2AUSIRK) Pulsed neutron generator of the IRK. 2173800100010 (FWHM ~ 0.7 nsec, repetition frequency 2.5 MHz) 2173800100011 INC-SOURCE (D-T) Deuteron-tritium reaction on titanium- 2173800100012 tritium target. 2173800100013 INC-SPECT Total neutron production rate of 1.4 x 10**17/sec 2173800100014 SAMPLE Shell shaped natural iron sample. 2173800100015 METHOD (TOF) Flight paths 30 cm (for the gammas) and 2173800100016 130 cm (for the neutrons). This allows a 2173800100017 considerable background reduction. 2173800100018 (COINC,PHD,PSD) A neutron-gamma coincidence is 2173800100019 recorded only if a 4-fold coincidence takes place. 2173800100020 -The neutrons are identified in the neutron detector 2173800100021 by pulse shape discrimination. 2173800100022 -The neutron pulse is only accepted if it 2173800100023 exceeds the threshold corresponding to a proton 2173800100024 energy of 350 keV. 2173800100025 -The gamma event is checked against its time-of- 2173800100026 flight and against coincidence with a neutron. 2173800100027 -The gamma pulse height should Be within the 2173800100028 range selected for the measurement. 2173800100029 -The neutron T.O.F. may not exceed the value for 2173800100030 a 1.4 MeV neutron. 2173800100031 DETECTOR (COIN,SCIN,NAICR) 12.5*2.5 cm**2 NE213 liquid 2173800100032 scintillator (neutrons) in coincidence with a 2173800100033 7.5*7.5 cm**2 Na-I-crystal (gammas). 2173800100034 (SCIN ) plastic scintillator to monitor the 2173800100035 neutron flux. It is calibrated using the 2173800100036 Al(n,alpha) reaction. 2173800100037 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2173800100038 The monitor error is 0.23% but the 2173800100039 calibration error is 3%. 2173800100040 MONIT-REF (20111002,H.Vonach+,J,ZP,237,(2),155,197009) 2173800100041 PART-DET (N) Neutrons from inelastic scattering, 2173800100042 (G) in coincidence with gamma radiation to the 2173800100043 ground state. 2173800100044 COMMENT Compared with statistical model calculations. 2173800100045 CORRECTION Background. 2173800100046 Chance coincidences. 2173800100047 Dead time effects. 2173800100048 Anisotropy of the (n,inl) reaction. This correction 2173800100049 is maximum 12%. 2173800100050 Finite sample thickness. 2173800100051 Multiple inelastic scattering. 2173800100052 Primary neutron flux attenuation. 2173800100053 Increase of the mean neutron path length by elastic 2173800100054 scattering. This correction amounts maximum to 10% 2173800100055 Presence of 5.8% (natural abundance) Fe-54 in the 2173800100056 sample to obtain the Fe-56 cross section from 2173800100057 the natural Fe cross section. This is done by 2173800100058 a theoretical calculation. 2173800100059 ERR-ANALYS (ERR-T) Total error given. It includes statistics 2173800100060 and all systematic errors from the corrections. 2173800100061 (ERR-1) Uncertainty of the efficiency of the neutron 2173800100062 detector 2173800100063 (ERR-2,,2.) Uncertainty of dead time 2173800100064 STATUS (TABLE) Table 2 from Nucl.Phys.,A290(1977)109 2173800100065 HISTORY (19810211C) G.C. 2173800100066 (20160725A) SD:Updated to new date formats,lower case. 2173800100067 Refs (including MONIT-REF) corrected (issue numb. 2173800100068 put in brackets). Small corrections in all Subents. 2173800100069 (20200807U) SD: Ref. corrected (OAW,114,-> OSA,114,) 2173800100070 ENDBIB 68 0 2173800100071 COMMON 3 3 2173800100072 EN MONIT ERR-1 2173800100073 MEV MB PER-CENT 2173800100074 14. 117. 1.4 2173800100075 ENDCOMMON 3 0 2173800100076 ENDSUBENT 75 0 2173800199999 SUBENT 21738002 20160725 22522173800200001 BIB 1 1 2173800200002 REACTION (26-FE-0(N,INL)26-FE-0,,DE) 2173800200003 ENDBIB 1 0 2173800200004 NOCOMMON 0 0 2173800200005 DATA 3 24 2173800200006 E DATA ERR-T 2173800200007 MEV MB/MEV MB/MEV 2173800200008 0.465 545. 22. 2173800200009 0.71 550. 22. 2173800200010 0.955 540. 20. 2173800200011 1.20 477. 20. 2173800200012 1.45 443. 18. 2173800200013 1.695 387. 18. 2173800200014 1.94 350. 14. 2173800200015 2.19 313. 14. 2173800200016 2.44 268. 11. 2173800200017 2.69 236. 11. 2173800200018 2.94 207. 8. 2173800200019 3.19 179. 8. 2173800200020 3.44 148. 6. 2173800200021 3.69 136. 6. 2173800200022 4.06 120. 6. 2173800200023 4.56 101. 6. 2173800200024 5.06 83.5 8. 2173800200025 5.56 78. 10. 2173800200026 6.07 52.5 10. 2173800200027 6.57 38.8 8. 2173800200028 7.07 34. 6. 2173800200029 7.57 27.4 5. 2173800200030 8.08 25.6 4. 2173800200031 8.58 17.4 3. 2173800200032 ENDDATA 26 0 2173800200033 ENDSUBENT 32 0 2173800299999 SUBENT 21738003 20160725 22522173800300001 BIB 1 1 2173800300002 REACTION (26-FE-56(N,INL)26-FE-56,,DE) 2173800300003 ENDBIB 1 0 2173800300004 NOCOMMON 0 0 2173800300005 DATA 3 24 2173800300006 E DATA ERR-T 2173800300007 MEV MB/MEV MB/MEV 2173800300008 0.465 570. 22. 2173800300009 0.71 574. 22. 2173800300010 0.955 556. 20. 2173800300011 1.20 491. 20. 2173800300012 1.45 455. 18. 2173800300013 1.695 399. 18. 2173800300014 1.94 356. 14. 2173800300015 2.19 316. 14. 2173800300016 2.44 272. 11. 2173800300017 2.69 246. 11. 2173800300018 2.94 209. 8. 2173800300019 3.19 181. 8. 2173800300020 3.44 149.5 6. 2173800300021 3.69 137.5 6. 2173800300022 4.06 121. 6. 2173800300023 4.56 102. 6. 2173800300024 5.06 84.5 8. 2173800300025 5.56 78.8 10. 2173800300026 6.07 53. 10. 2173800300027 6.57 39.2 8. 2173800300028 7.07 34.3 6. 2173800300029 7.57 27.7 5. 2173800300030 8.08 25.8 4. 2173800300031 8.58 17.6 3. 2173800300032 ENDDATA 26 0 2173800300033 ENDSUBENT 32 0 2173800399999 ENDENTRY 3 0 2173899999999