ENTRY 41777 20241226 4177700000001 SUBENT 41777001 20241226 20250711 4177700100001 BIB 13 45 4177700100002 TITLE The energy dependence of the temporal parameters of 4177700100003 delayed neutrons from the neutron-induced fission of 4177700100004 235U in the energy range from 0.4 to 8 MeV 4177700100005 AUTHOR (D.E.Gremyachkin,A.S.Egorov,K.V.Mitrofanov, 4177700100006 V.F.Mitrofanov, V.M.Piksaikin, I.P.Bondarenko) 4177700100007 REFERENCE (J,ANE,211,110904,2025) 4177700100008 #doi:10.1016/j.anucene.2024.110904 4177700100009 INSTITUTE (4RUSFEI) 4177700100010 REL-REF (O,F1525000,D.E.Gremyachkin+,J,ANE,211,110904,2025) 4177700100011 Charge particle induced data of this article. 4177700100012 FACILITY (ACCEL,4RUSFEI) 6-MeV electrostatic accelerator 4177700100013 INC-SOURCE (P-LI7) For neutron energy 0.42 - 2.92 MeV. 4177700100014 Targets - LiF evaporated on 0.5-mm thick copper 4177700100015 backings. 4177700100016 (D-D) For neutron energy 4 - 8 MeV. 4177700100017 Targets - deuterium absorbed in ~1 mg/cm2 thick Ti 4177700100018 layer deposited on 0.5 mm thick copper backings. 4177700100019 .Energy loss in the target does not exceed the neutron 4177700100020 kinematic energy spread. 4177700100021 INC-SPECT Spectra are presented on Figs.2 (p-Li7),3 (d-d). 4177700100022 METHOD (ACTIV) Cyclic irradiation followed by the measurement 4177700100023 of the time dependence of delayed neutron activity. 4177700100024 Irradiation time was 180 and 15s, DN counting time was 4177700100025 600 and 500 s, respectively; sample delivery time 4177700100026 200 ms. 4177700100027 DETECTOR (HE3SP) 4PI neutron detector - assembly of 21 4177700100028 proportional He3-counters distributed in polyethylene 4177700100029 moderator. Surrounded by Cd sheet and borated 4177700100030 polyethylene (10 cm thick). 4177700100031 Energy dependence of the 4PI detector absolute 4177700100032 efficiency was determined by 252Cf calibrated source 4177700100033 and calculated by Monte Carlo method. See Fig.6 . 4177700100034 Average efficiency (weighted by the 252Cf prompt 4177700100035 neutron spectrum) - 34.96+-0.81. 4177700100036 (FISCH) Fission chamber with Pu-239 deposit of 4177700100037 100 microg/cm2 was used as neutron flux monitor. 4177700100038 SAMPLE No information about U-235 sample in the article. 4177700100039 239Pu deposit of 100 mug/cm2 was used as the neutron 4177700100040 flux monitor. 4177700100041 CORRECTION For background. 4177700100042 For break-up neutrons. 4177700100043 For non-monoenergetic component of incident neutrons. 4177700100044 For background. 4177700100045 HISTORY (20241226C) M.M. 4177700100046 (20250116R) 4177700100047 ENDBIB 45 0 4177700100048 NOCOMMON 0 0 4177700100049 ENDSUBENT 48 0 4177700199999 SUBENT 41777002 20241226 20250711 4177700200001 BIB 5 17 4177700200002 REACTION (92-U-235(N,F),DL,NU) 4177700200003 ANALYSIS Analysis of DN decay curve was done by iterative 4177700200004 least-square method in frames of 6-group model. 4177700200005 Obtained data of HL(En) were used to estimate DN yield.4177700200006 ADD-RES Delayed neutrons precursors average HL dependence from4177700200007 incident neutron energy HL(En) is on Fig.10. 4177700200008 ERR-ANALYS Relative uncertainties of the activity values: 4177700200009 Uncertainty of the number of atoms in the 4177700200010 sample ~ 1.%. 4177700200011 Uncertainty of total delayed neutron yield ~5% 4177700200012 Uncertainty of neutron detection efficiency 2.3%4177700200013 Uncertainty of U235 fission cross section 1% 4177700200014 Uncertainty of flux density 5.3 % 4177700200015 (DATA-ERR) Type of uncertainty was not explained by 4177700200016 the authors. 4177700200017 STATUS (TABLE) From authors 4177700200018 Data are on Fig.11 of the article (black circles) 4177700200019 ENDBIB 17 0 4177700200020 NOCOMMON 0 0 4177700200021 DATA 3 14 4177700200022 EN DATA DATA-ERR 4177700200023 MEV PRT/FIS PRT/FIS 4177700200024 0.42 0.01565 6.54558E-4 4177700200025 0.47 0.01539 6.04944E-4 4177700200026 0.92 0.01576 6.96444E-4 4177700200027 1.92 0.01576 6.61550E-4 4177700200028 2.92 0.01569 6.22242E-4 4177700200029 4.0 0.01615 3.96647E-4 4177700200030 4.5 0.01635 5.87637E-4 4177700200031 5.0 0.01647 6.31231E-4 4177700200032 5.5 0.01627 5.83417E-4 4177700200033 6.0 0.01643 4.06772E-4 4177700200034 6.5 0.01510 5.88272E-4 4177700200035 7.0 0.01447 3.68440E-4 4177700200036 7.5 0.01385 5.76286E-4 4177700200037 8.0 0.01231 3.15116E-4 4177700200038 ENDDATA 16 0 4177700200039 ENDSUBENT 38 0 4177700299999 ENDENTRY 2 0 4177799999999