ENTRY 41582 20181224 418141582 0 1 SUBENT 41582001 20181224 418141582 1 1 BIB 8 41 41582 1 2 TITLE Radionuclide neutron source on the base of 41582 1 3 californium-252. 41582 1 4 AUTHOR (Uy.I.Kolevatov, L.A.Trykov, V.S.Volkov) 41582 1 5 INSTITUTE (4RUSFEI) 41582 1 6 REFERENCE (R,FEI-913,1979) Main reference . 41582 1 7 (R,FEI-1730,1985) First author L.Trykov. 41582 1 8 "Methods of spectrometers calibration by means of 41582 1 9 radionuclide neutron sources". 41582 1 10 FACILITY Setup was consisted of Cf source, detector and 41582 1 11 protecting cone to measure background 41582 1 12 - of polyethylene for neutron background, 41582 1 13 - of lead for gamma background. 41582 1 14 SAMPLE #1. Source of 1.7 mm diameter, 36 mm high. 41582 1 15 #2. Source was packed in steel ampule of 8mm diameter,41582 1 16 40 mm high. 41582 1 17 #3. Source was packed in double ampule 41582 1 18 - first of 10 mm diameter, 8 mm high, stainless steel, 41582 1 19 - second of cooper, 15 mm diameter, 14 mm high. 41582 1 20 #4. Source consisted of four separate sources in 41582 1 21 stainless steel ampule; packed in steel ampule of 20mm41582 1 22 diameter, 30 mm high. 41582 1 23 #5. Source #1 of 1.7 mm diameter, 36 mm high, packed 41582 1 24 in steel cylinder of 15 mm diameter, 25 mm high; 41582 1 25 used to check influence of source construction 41582 1 26 elements on the shape of neutron spectrum. 41582 1 27 Activity of sources, n/s: 41582 1 28 measured by passport at measurement time 41582 1 29 #1 (1.5+-0.1)E+6 (1.7+-0.17)E+6 41582 1 30 #2 (4.2+-0.3)E+6 (4.4+-0.2)E+6 41582 1 31 #3 (4.8+-0.4)E+8 (5.5+-0.55)E+8 41582 1 32 #4 (9.5+-0.8)E+8 (1.0+-0.1)E+9 41582 1 33 DETECTOR (SCIN) Single crystal spectrometer with stilbene 41582 1 34 crystals of size 5x7, 10x10, 30x30 mm and PTF crystal 41582 1 35 of size 19x10 mm. 41582 1 36 For gamma spectra measurement - stilbene crystal of 41582 1 37 size 40x40 mm. 41582 1 38 Energy resolution of spectrometer 1-2 %. 41582 1 39 HISTORY (20111215C) M.M. 41582 1 40 (20120512A) DOI code was corrected in Subent 003 41582 1 41 according to WP2012-26 . 41582 1 42 (20181224A) Reaction in Subent 005 was corrected. 41582 1 43 ENDBIB 41 0 41582 1 44 NOCOMMON 0 0 41582 1 45 ENDSUBENT 44 0 41582 199999 SUBENT 41582002 20111215 41554158200200001 BIB 3 9 4158200200002 REACTION (98-CF-252(0,F)0-NN-1,,KEM,,RAW) 4158200200003 ANALYSIS Neutron energy region of measurement 0.5 - 15. MeV. 4158200200004 Shape of measured spectra was well described by 4158200200005 Maxwellian distribution of T=1.40+-0.02 4158200200006 for all sources in energy range E > 3. MeV , 4158200200007 for source #1 in energy range E > 0.5 MeV. 4158200200008 For sources #2, 3, 4 in energy range E < 3.MeV there 4158200200009 is deviation from Maxwellian distribution. 4158200200010 STATUS (TABLE) Table 1 of R,FEI-913 . 4158200200011 ENDBIB 9 0 4158200200012 NOCOMMON 0 0 4158200200013 DATA 2 1 4158200200014 DATA DATA-ERR 4158200200015 MEV MEV 4158200200016 1.40 0.02 4158200200017 ENDDATA 3 0 4158200200018 ENDSUBENT 17 0 4158200299999 SUBENT 41582003 20120512 41574158200300001 BIB 6 17 4158200300002 REACTION (98-CF-252(0,F)0-G-0,PAR,KE,,RAW) Average gamma energy 4158200300003 of Cf sources spectra. 4158200300004 MISC-COL (MISC1) Gamma yield per one neutron, gamma/neutron. 4158200300005 (MISC2) Total gamma energy per one neutron, MEV/neutron4158200300006 ASSUMED (ASSUM,98-CF-252(0,F),,NU) Used for comparison of 4158200300007 MISC1 and MISC2 with other experiments. 4158200300008 REL-REF (A,,K.Skarsvag,J,NP/A,153,82,1970) 4158200300009 #doi:10.1016/0375-9474(70)90757-8 4158200300010 3.07+-0.26 gammas/neutron for Cf . 4158200300011 A.Kraut, Dostizheniya fiziki deleniya yader, in book 4158200300012 Fizika deleniya yader, translation from Engl., 4158200300013 Gosatomizdat, 1963 . 4158200300014 2.72 gammas/neutron, 2.17 MeV/neutron, 0.8 MeV for Cf. 4158200300015 FLAG (1.) Cf source #1. 4158200300016 (3.) Cf source #3. 4158200300017 (4.) Cf source #4. 4158200300018 STATUS (TABLE) Table 3 of R,FEI-913 . 4158200300019 ENDBIB 17 0 4158200300020 COMMON 1 3 4158200300021 ASSUM 4158200300022 PRT/FIS 4158200300023 3.78 4158200300024 ENDCOMMON 3 0 4158200300025 DATA 8 3 4158200300026 E-MIN E-MAX DATA MISC1 MISC1-ERR MISC2 4158200300027 MISC2-ERR FLAG 4158200300028 MEV MEV MEV SEE TEXT SEE TEXT SEE TEXT 4158200300029 SEE TEXT NO-DIM 4158200300030 0.4 9. 1.1 15.4 2.3 17.0 4158200300031 2.6 1. 4158200300032 0.4 9. 1.1 4.0 0.6 4.42 4158200300033 0.66 3. 4158200300034 0.4 5. 1.2 2.5 0.4 3.2 4158200300035 0.5 4. 4158200300036 ENDDATA 10 0 4158200300037 ENDSUBENT 36 0 4158200399999 SUBENT 41582004 20111215 41554158200400001 BIB 6 22 4158200400002 REACTION (98-CF-252(0,F),,NU/DE,,RAW) Neutron spectrum. 4158200400003 Data units given in title of table are n/(sec*MeV), 4158200400004 Cf source yield normalized to 10**9 n/sec . 4158200400005 ANALYSIS Energy neutron spectrum was defined as: 4158200400006 f(E)=4*PI*R**2*F(E)*10**-9 . 4158200400007 COMMENT Of compiler. Integral of this data by E in given 4158200400008 energy range is about 10. . 4158200400009 CRITIQUE Of compiler. In R,FEI-1730 it's not mentioned: 4158200400010 what Cf source was used for this data measurement; 4158200400011 any corrections were applied. 4158200400012 On Fig. 12 of R,FEI-1730 two spectra are presented - 4158200400013 for 1.92E+7 n/s activity Cf source , 4158200400014 for 6.0E+8 n/s activity Cf source ( normalized to 4158200400015 1.92E+7 n/s yield); 4158200400016 quality of figures does not let to split these two 4158200400017 spectra by digitizing. 4158200400018 On Fig.1 of R,FEI-913 spectra are presented for 4158200400019 samples # 1-4 as shape data. 4158200400020 ERR-ANALYS (ERR-SYS,,5.) Total systematical error. 4158200400021 Total error (taking into account also statistics) is 4158200400022 2-3 times higher. 4158200400023 STATUS (TABLE) Table 1 of R,FEI-1730 . 4158200400024 ENDBIB 22 0 4158200400025 NOCOMMON 0 0 4158200400026 DATA 3 48 4158200400027 E-MIN E-MAX DATA 4158200400028 MEV MEV ARB-UNITS 4158200400029 0.1 0.2 2.40 4158200400030 0.2 0.3 2.81 4158200400031 0.3 0.4 3.67 4158200400032 0.4 0.5 3.28 4158200400033 0.5 0.6 3.64 4158200400034 0.6 0.7 3.84 4158200400035 0.7 0.8 3.60 4158200400036 0.8 0.9 3.83 4158200400037 0.9 1.0 3.53 4158200400038 1.0 1.1 3.50 4158200400039 1.1 1.2 3.44 4158200400040 1.2 1.3 3.44 4158200400041 1.3 1.4 3.06 4158200400042 1.4 1.5 3.13 4158200400043 1.5 1.6 2.88 4158200400044 1.6 1.7 2.73 4158200400045 1.7 1.8 2.57 4158200400046 1.8 1.9 2.45 4158200400047 1.9 2.0 2.33 4158200400048 2.0 2.2 2.13 4158200400049 2.2 2.4 1.96 4158200400050 2.4 2.6 1.84 4158200400051 2.6 2.8 1.69 4158200400052 2.8 3.0 1.48 4158200400053 3.0 3.2 1.22 4158200400054 3.2 3.4 1.09 4158200400055 3.4 3.6 0.975 4158200400056 3.6 3.8 0.875 4158200400057 3.8 4.0 0.800 4158200400058 4.0 4.5 0.638 4158200400059 4.5 5.0 0.466 4158200400060 5.0 5.5 0.350 4158200400061 5.5 6.0 0.234 4158200400062 6.0 6.5 0.178 4158200400063 6.5 7.0 0.138 4158200400064 7.0 7.5 0.0938 4158200400065 7.5 8.0 0.0563 4158200400066 8.0 8.5 0.050 4158200400067 8.5 9.0 0.0349 4158200400068 9.0 9.5 0.025 4158200400069 9.5 10.0 0.0188 4158200400070 10.0 10.5 0.0115 4158200400071 10.5 11.0 0.00886 4158200400072 11.0 11.5 0.00677 4158200400073 11.5 12.0 0.00469 4158200400074 12.0 12.5 0.00354 4158200400075 12.5 13.0 0.00245 4158200400076 13.0 13.5 0.00188 4158200400077 ENDDATA 50 0 4158200400078 ENDSUBENT 77 0 4158200499999 SUBENT 41582005 20181224 418141582 5 1 BIB 6 16 41582 5 2 REACTION (98-CF-252(0,F)0-G-0,PR,FY/DE,,RAW) Gamma spectrum. 41582 5 3 Data units given in title of table are gamma/(sec*MeV)41582 5 4 Cf source yield normalized to 10**9 n/sec . 41582 5 5 ANALYSIS Energy gamma spectrum was defined as: 41582 5 6 f(E)=4*PI*R**2*F(E) . 41582 5 7 CRITIQUE It's not mentioned in R,FEI-1730, what Cf source was 41582 5 8 used for these data measurement. 41582 5 9 On Fig.3 of R,FEI-913 gamma spectra for samples # 1,3,441582 5 10 are presented. 41582 5 11 Data given in data block looks like the data given on 41582 5 12 Fig.3 of R,FEI-913 for sample #3 - in shape. 41582 5 13 ERR-ANALYS (DATA-ERR,,20.) Total error 41582 5 14 STATUS (TABLE) Table 7 of Rep.FEI-1730 . 41582 5 15 HISTORY (20181224A) Reaction was corrected 41582 5 16 0-G-0,,MLT/DE,,RAW) -> 0-G-0,PR,FY/DE,,RAW) 41582 5 17 according to a comment of N.Otsuka ( NDS, IAEA) 41582 5 18 ENDBIB 16 0 41582 5 19 NOCOMMON 0 0 41582 5 20 DATA 2 42 41582 5 21 E DATA 41582 5 22 MEV ARB-UNITS 41582 5 23 0.4646 5.3 E+9 41582 5 24 0.5768 5.4 E+9 41582 5 25 0.6859 4.0 E+9 41582 5 26 0.7930 3.1 E+9 41582 5 27 0.8986 2.37 E+9 41582 5 28 1.0033 2.05 E+9 41582 5 29 1.1073 1.51 E+9 41582 5 30 1.2106 1.56 E+9 41582 5 31 1.3135 1.49 E+9 41582 5 32 1.4161 1.04 E+9 41582 5 33 1.5183 0.86 E+9 41582 5 34 1.6203 0.81 E+9 41582 5 35 1.7221 0.70 E+9 41582 5 36 1.8237 0.53 E+9 41582 5 37 1.9262 0.58 E+9 41582 5 38 2.0265 0.55 E+9 41582 5 39 2.1277 0.47 E+9 41582 5 40 2.2793 0.39 E+9 41582 5 41 2.4812 0.32 E+9 41582 5 42 2.6829 0.26 E+9 41582 5 43 2.8843 0.30 E+9 41582 5 44 3.0855 0.159 E+9 41582 5 45 3.2866 0.103 E+9 41582 5 46 3.4876 0.88 E+8 41582 5 47 3.6885 0.76 E+8 41582 5 48 3.8893 0.51 E+8 41582 5 49 4.0900 0.40 E+8 41582 5 50 4.3408 0.32 E+8 41582 5 51 4.6417 0.189 E+8 41582 5 52 4.9425 0.135 E+8 41582 5 53 5.2432 0.970 E+7 41582 5 54 5.5438 0.400 E+7 41582 5 55 5.8443 0.284 E+7 41582 5 56 6.1448 0.350 E+7 41582 5 57 6.4453 0.140 E+7 41582 5 58 6.7457 0.59 E+6 41582 5 59 7.0461 0.291 E+6 41582 5 60 7.3464 0.259 E+6 41582 5 61 7.6968 0.220 E+6 41582 5 62 8.0972 0.252 E+6 41582 5 63 8.4976 0.558 E+5 41582 5 64 8.8979 0.153 E+5 41582 5 65 ENDDATA 44 0 41582 5 66 ENDSUBENT 65 0 41582 599999 ENDENTRY 5 0 4158299999999