ENTRY 41582 20181224 41814158200000001 SUBENT 41582001 20181224 41814158200100001 BIB 8 41 4158200100002 TITLE Radionuclide neutron source on the base of 4158200100003 californium-252. 4158200100004 AUTHOR (Uy.I.Kolevatov, L.A.Trykov, V.S.Volkov) 4158200100005 INSTITUTE (4RUSFEI) 4158200100006 REFERENCE (R,FEI-913,1979) Main reference . 4158200100007 (R,FEI-1730,1985) First author L.Trykov. 4158200100008 "Methods of spectrometers calibration by means of 4158200100009 radionuclide neutron sources". 4158200100010 FACILITY Setup was consisted of Cf source, detector and 4158200100011 protecting cone to measure background 4158200100012 - of polyethylene for neutron background, 4158200100013 - of lead for gamma background. 4158200100014 SAMPLE #1. Source of 1.7 mm diameter, 36 mm high. 4158200100015 #2. Source was packed in steel ampule of 8mm diameter,4158200100016 40 mm high. 4158200100017 #3. Source was packed in double ampule 4158200100018 - first of 10 mm diameter, 8 mm high, stainless steel, 4158200100019 - second of cooper, 15 mm diameter, 14 mm high. 4158200100020 #4. Source consisted of four separate sources in 4158200100021 stainless steel ampule; packed in steel ampule of 20mm4158200100022 diameter, 30 mm high. 4158200100023 #5. Source #1 of 1.7 mm diameter, 36 mm high, packed 4158200100024 in steel cylinder of 15 mm diameter, 25 mm high; 4158200100025 used to check influence of source construction 4158200100026 elements on the shape of neutron spectrum. 4158200100027 Activity of sources, n/s: 4158200100028 measured by passport at measurement time 4158200100029 #1 (1.5+-0.1)E+6 (1.7+-0.17)E+6 4158200100030 #2 (4.2+-0.3)E+6 (4.4+-0.2)E+6 4158200100031 #3 (4.8+-0.4)E+8 (5.5+-0.55)E+8 4158200100032 #4 (9.5+-0.8)E+8 (1.0+-0.1)E+9 4158200100033 DETECTOR (SCIN) Single crystal spectrometer with stilbene 4158200100034 crystals of size 5x7, 10x10, 30x30 mm and PTF crystal 4158200100035 of size 19x10 mm. 4158200100036 For gamma spectra measurement - stilbene crystal of 4158200100037 size 40x40 mm. 4158200100038 Energy resolution of spectrometer 1-2 %. 4158200100039 HISTORY (20111215C) M.M. 4158200100040 (20120512A) DOI code was corrected in Subent 003 4158200100041 according to WP2012-26 . 4158200100042 (20181224A) Reaction in Subent 005 was corrected. 4158200100043 ENDBIB 41 0 4158200100044 NOCOMMON 0 0 4158200100045 ENDSUBENT 44 0 4158200199999 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 33 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 41814158200500001 BIB 6 16 4158200500002 REACTION (98-CF-252(0,F)0-G-0,PR,FY/DE,,RAW) Gamma spectrum. 4158200500003 Data units given in title of table are gamma/(sec*MeV)4158200500004 Cf source yield normalized to 10**9 n/sec . 4158200500005 ANALYSIS Energy gamma spectrum was defined as: 4158200500006 f(E)=4*PI*R**2*F(E) . 4158200500007 CRITIQUE It's not mentioned in R,FEI-1730, what Cf source was 4158200500008 used for these data measurement. 4158200500009 On Fig.3 of R,FEI-913 gamma spectra for samples # 1,3,44158200500010 are presented. 4158200500011 Data given in data block looks like the data given on 4158200500012 Fig.3 of R,FEI-913 for sample #3 - in shape. 4158200500013 ERR-ANALYS (DATA-ERR,,20.) Total error 4158200500014 STATUS (TABLE) Table 7 of Rep.FEI-1730 . 4158200500015 HISTORY (20181224A) Reaction was corrected 4158200500016 0-G-0,,MLT/DE,,RAW) -> 0-G-0,PR,FY/DE,,RAW) 4158200500017 according to a comment of N.Otsuka ( NDS, IAEA) 4158200500018 ENDBIB 16 0 4158200500019 NOCOMMON 0 0 4158200500020 DATA 2 42 4158200500021 E DATA 4158200500022 MEV ARB-UNITS 4158200500023 0.4646 5.3 E+9 4158200500024 0.5768 5.4 E+9 4158200500025 0.6859 4.0 E+9 4158200500026 0.7930 3.1 E+9 4158200500027 0.8986 2.37 E+9 4158200500028 1.0033 2.05 E+9 4158200500029 1.1073 1.51 E+9 4158200500030 1.2106 1.56 E+9 4158200500031 1.3135 1.49 E+9 4158200500032 1.4161 1.04 E+9 4158200500033 1.5183 0.86 E+9 4158200500034 1.6203 0.81 E+9 4158200500035 1.7221 0.70 E+9 4158200500036 1.8237 0.53 E+9 4158200500037 1.9262 0.58 E+9 4158200500038 2.0265 0.55 E+9 4158200500039 2.1277 0.47 E+9 4158200500040 2.2793 0.39 E+9 4158200500041 2.4812 0.32 E+9 4158200500042 2.6829 0.26 E+9 4158200500043 2.8843 0.30 E+9 4158200500044 3.0855 0.159 E+9 4158200500045 3.2866 0.103 E+9 4158200500046 3.4876 0.88 E+8 4158200500047 3.6885 0.76 E+8 4158200500048 3.8893 0.51 E+8 4158200500049 4.0900 0.40 E+8 4158200500050 4.3408 0.32 E+8 4158200500051 4.6417 0.189 E+8 4158200500052 4.9425 0.135 E+8 4158200500053 5.2432 0.970 E+7 4158200500054 5.5438 0.400 E+7 4158200500055 5.8443 0.284 E+7 4158200500056 6.1448 0.350 E+7 4158200500057 6.4453 0.140 E+7 4158200500058 6.7457 0.59 E+6 4158200500059 7.0461 0.291 E+6 4158200500060 7.3464 0.259 E+6 4158200500061 7.6968 0.220 E+6 4158200500062 8.0972 0.252 E+6 4158200500063 8.4976 0.558 E+5 4158200500064 8.8979 0.153 E+5 4158200500065 ENDDATA 44 0 4158200500066 ENDSUBENT 65 0 4158200599999 ENDENTRY 5 0 4158299999999