ENTRY 41507 20141015 41654150700000001 SUBENT 41507001 20141015 41654150700100001 BIB 14 57 4150700100002 TITLE Study of the high-energy part spectrum of gamma-rays 4150700100003 from the neutron-induced fission reaction 4150700100004 AUTHOR (V.A.Varlachev, G.N.Dudkin, V.N.Padalko) 4150700100005 INSTITUTE (4RUSTPI) Institute of nuclear physics, Tomsk, Russia 4150700100006 REFERENCE (J,IZV,71,(11),1675,200711) Main ref. 4150700100007 (J,BAS,71,(11),1635,200711) Engl.translation of IZV,71 4150700100008 (J,ZEP,82,(7),440,2005) Prelim.publication. 4150700100009 (J,JEL,82,390,2005) Engl.translation of J,ZEP. 4150700100010 FACILITY (REAC,4RUSTPI) 4150700100011 INC-SOURCE (REAC) 6 MWt power. 4150700100012 INC-SPECT Reactor spectrum. EN-DUMMY was proposed by compiler 4150700100013 as thermal. 4150700100014 SAMPLE U-235 of reactor active zone. 4150700100015 DETECTOR (NAICR) NaI(Tl) spectrometer with crystal of 200 mm 4150700100016 diameter, 200 mm length. 4150700100017 Protected by distilled water filter of 300 cm 4150700100018 thickness. Two lead collimators with hole of 2 cm 4150700100019 diameter and 15 cm length in each. 4150700100020 Gamma quantum intensity in detector position - 4150700100021 5E+04 gammas/sec. 4150700100022 (SCIN) Scintillation detectors system around the 4150700100023 NaI-spectrometer. Used in anti-coincidence with NAICR.4150700100024 Calibration of spectrometer was made by gamma-lines 4150700100025 (1.33 MeV) of Co-60 source, by 7.72 , 7.64 MeV gamma 4150700100026 lines from radiative neutron capture on Al and Fe; 4150700100027 resolution was defined to be 11% and 7.7%, 4150700100028 respectively .In energy range 30-100 MeV the electron4150700100029 beam of synchrotron SIRIUS was used. 4150700100030 Registration efficiency 95 % in 1-10 MeV gamma energy4150700100031 range, and 85% for higher energies. 4150700100032 Oscilloscope "Tektronix-TDS 2014" was used in 4150700100033 measurements to exclude superpositions of pulses. 4150700100034 METHOD (GSPEC) Gamma energy spectrum was measured. 4150700100035 PART-DET (G) Gammas from the process of bremsstrahlung of FF. 4150700100036 DECAY-DATA (27-CO-60,,DG,1170.,,DG,1330.) + sum peak 2.5 MeV 4150700100037 (28-NI-59,,DG,11380.) 4150700100038 Cr - 1.78, 1.79 MeV, H - 2.2 MeV, Be - 6.8 MeV, 4150700100039 Ti - 6.76 MeV, Al - 7.72 MeV, Fe - 7.64 MeV, 4150700100040 Cr and Ni - 8.8 MeV, 8.9 MeV, Cr - 9.7 MeV, 11.3 MeV, 4150700100041 The book of V.I.Gumma, A.M.Demidov+ "Neutron radiation4150700100042 analysis", Moscow, Energoatomizdat,1984, was used for 4150700100043 gamma spectra analysis. 4150700100044 ANALYSIS Ratio of pulse area to pulse-height was used. 4150700100045 Gamma spectrum at energy range 12 - 20 MeV was fitted4150700100046 by exponent and two Gaussians of 11.38 and 15.04 MeV. 4150700100047 Calculated parameters, used in analysis: 4150700100048 - Solid angle of detector 1.26E-05 steradian, 4150700100049 - Intensity of fissions 4.8E+15 fissions/sec, 4150700100050 - Coefficient for gamma absorption in water filter and4150700100051 materials of reactor zone - (1.1 - 4.4)E-3, 4150700100052 - Efficiency of gamma registration by NaI(Tl)-spectro-4150700100053 meter - 0.85, assumed not dependent from energy. 4150700100054 HISTORY (20080402C) Compiled at CJD. M.M. 4150700100055 (20101215U) Opening parenthesis was moved in 12 column.4150700100056 (20110325A) Ref. J,ZEP,82,(7),440,2005 and Engl. 4150700100057 translation were added. 4150700100058 (20141015A) Code PR was added in REACTIONs. 4150700100059 ENDBIB 57 0 4150700100060 COMMON 1 3 4150700100061 EN-DUMMY 4150700100062 EV 4150700100063 0.025 4150700100064 ENDCOMMON 3 0 4150700100065 ENDSUBENT 64 0 4150700199999 SUBENT 41507002 20141015 41654150700200001 BIB 5 15 4150700200002 REACTION (92-U-235(N,F)0-G-0,PR,FY/DE,,RAW) 4150700200003 Gamma multiplicity. 4150700200004 EN-SEC (E,G) Energy of gammas from the process of 4150700200005 bremsstrahlung of fission fragments. 4150700200006 ERR-ANALYS (ERR-S) Statistical error. 4150700200007 E-RSL - gamma energy resolution of spectrometer. 4150700200008 (E-ERR-DIG) Digitizing error of E 4150700200009 (ERR-DIG) Digitizing error of DATA 4150700200010 STATUS (CURVE) Data are on Fig.6 of IZV,71,(11),1675,2007 4150700200011 (APRVD) Reply 04.04.2008 from author G.N.Dudkin: 4150700200012 "Digitized data coincide with author's. No additions, 4150700200013 corrections or comments." 4150700200014 HISTORY (20110614A) Correction according to N.Otsuka's comment 4150700200015 (NDS IAEA): 4150700200016 "),,MLT/DE,,TT" -> ")0-G-0,,FY/DE,,RAW" . 4150700200017 ENDBIB 15 0 4150700200018 COMMON 3 3 4150700200019 E-RSL E-ERR-DIG ERR-DIG 4150700200020 PER-CENT MEV PER-CENT 4150700200021 8. 0.22385E-01 0.17E-01 4150700200022 ENDCOMMON 3 0 4150700200023 DATA 3 13 4150700200024 E DATA ERR-S 4150700200025 MEV PT/FIS/MEV PT/FIS/MEV 4150700200026 11.34 0.38670E-04 4150700200027 13.09 0.12737E-04 4150700200028 14.11 0.94901E-05 4150700200029 15.37 0.58026E-05 4150700200030 16.98 0.19583E-05 4150700200031 19.05 0.39314E-06 4150700200032 22.04 0.60258E-07 4150700200033 24.98 0.99485E-08 4150700200034 26.92 0.18530E-08 0.4066E-09 4150700200035 28.64 0.58073E-09 0.1274E-09 4150700200036 30.95 0.16514E-09 0.5730E-10 4150700200037 32.98 0.57214E-10 0.2581E-10 4150700200038 36.13 0.23673E-10 0.9011E-11 4150700200039 ENDDATA 15 0 4150700200040 ENDSUBENT 39 0 4150700299999 SUBENT 41507003 20141015 41654150700300001 BIB 5 11 4150700300002 REACTION (92-U-235(N,F)0-G-0,PR/PAR,FY,,RAW) 4150700300003 Upper limit of gamma yield at gamma energy range from4150700300004 E-MIN to E-MAX. 4150700300005 EN-SEC (E-MAX,G) Maximal gamma energy. 4150700300006 (E-MIN,G) Minimal gamma energy. 4150700300007 ANALYSIS Data from additional 24-hours measurement were analyzed4150700300008 by statistical analysis based on Puasson statistics. 4150700300009 STATUS (TABLE) Text of J,IZV,71,(11),1675,2007, p.1678. 4150700300010 HISTORY (20110614A) Correction "),PAR,MLT,G,TT" -> 4150700300011 ")0-G-0,PAR,FY,,RAW" 4150700300012 according to N.Otsuka's comment (NDS IAEA). 4150700300013 ENDBIB 11 0 4150700300014 NOCOMMON 0 0 4150700300015 DATA 3 1 4150700300016 E-MIN E-MAX DATA-MAX 4150700300017 MEV MEV PRT/FIS 4150700300018 36. 90. 0.9E-10 4150700300019 ENDDATA 3 0 4150700300020 ENDSUBENT 19 0 4150700399999 ENDENTRY 3 0 4150799999999