ENTRY 41714 20201120 41914171400000001 SUBENT 41714001 20201120 41914171400100001 BIB 15 51 4171400100002 TITLE Fission of 239Pu by resonance neutrons 4171400100003 AUTHOR (V.Polhorsky,J.Kliman,J.Kristiak,A.A.Bogdzel, 4171400100004 N.A.Gundorin,A.V.Popov,U.Gohs) 4171400100005 INSTITUTE (4ZZZDUB) A.A.Bogdzel,N.A.Gundorin,A.V.Popov 4171400100006 (3SLKSLO) V.Polhorski,J.Kliman,J.Kristiak 4171400100007 (2GERDRE) U.Gohs 4171400100008 REFERENCE (J,YF,57,1198,1994) Issue 7. In English. 4171400100009 (J,PAN,57,1132,1994) The same as YF,57,1198 4171400100010 (J,CZJ,43,783,1993) Issue 8. Exp.details. 4171400100011 FACILITY (REAC,4ZZZDUB) IBR-30 fast pulse reactor 4171400100012 INC-SOURCE (REAC) 4171400100013 INC-SPECT Energy resolution 1.9E-3 * E**(3/2) 4171400100014 Neutron flux 8.3E+3*E**0.9 /(cm2*sec*eV) 4171400100015 Repetition rate 100 Hz 4171400100016 Recycled neutron energy 0.17 eV 4171400100017 SAMPLE Total mass 1.6 g, 19 layers, enrichment 99.9%. 4171400100018 Placed in ionization chamber. 4171400100019 DECAY-DATA (94-PU-239,2.4E+4YR) 4171400100020 METHOD (TOF) For incident neutron energy measurement. 4171400100021 Flight path 57 m. 4171400100022 (COINC) Coincidence of fission chamber and Ge(Li) 4171400100023 detectors within the controlled time window. 4171400100024 Three parameters were measured 4171400100025 - incident neutrons energy measured by time-of-flight, 4171400100026 - energy of the post-fission gamma-ray (prompt), 4171400100027 - the time between fission and gamma detection. 4171400100028 (GSPEC) Measured gamma spectrum was used for 4171400100029 identification of fission fragments. 4171400100030 Coincidence time window 32 nsec. 4171400100031 Time resolution of whole system 15 nsec. 4171400100032 PART-DET (FF,G) 4171400100033 DETECTOR (FISCH) 19 sections ionization fission chamber . 4171400100034 Working gas - isobutane at 20 torr pressure. 4171400100035 Fission fragments detection efficiency - 60%. 4171400100036 (GELI) Ge(Li)-detector for gammas. 4171400100037 Working volume 100 cm3, energy resolution (FWHM) 4171400100038 2.4 keV for 1333 keV. 4171400100039 Standard Ta-181, Eu-152, Ba-133, Ir-192, 4171400100040 Ag-110m, Y-88, Co-56, Cs-137, Hg-203, Zn-65, Na-22, 4171400100041 Mn-54, Am-241, Sn-113, Ce-139, Co-57, Co-60 were used 4171400100042 for absolute efficiency calibration and response 4171400100043 matrix. 4171400100044 Spectrometer absolute efficiency 7.E-4 at E=100 keV. 4171400100045 ADD-RES . The prescission average width for Pu-239 4171400100046 GAMMAgamma(1+)=4.8+-2.5 MeV was compared with data of 4171400100047 other authors. 4171400100048 . Charge dispersion was estimated to be 4171400100049 SIG**2=0.36+-0.03 4171400100050 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4171400100051 article. 4171400100052 HISTORY (20201125C) M.M. 4171400100053 ENDBIB 51 0 4171400100054 NOCOMMON 0 0 4171400100055 ENDSUBENT 54 0 4171400199999 SUBENT 41714002 20201120 41914171400200001 BIB 3 6 4171400200002 REACTION 1(94-PU-239(N,F)0-G-0,PR/PAR,FY,,SPA) 4171400200003 2(94-PU-239(N,F)0-G-0,PR/PAR,KE,,SPA) 4171400200004 Energy of all gammas 4171400200005 INC-SPECT Resonance neutrons of 0.2 - 230. eV energy range. 4171400200006 STATUS (TABLE) Text pages 786 of 4171400200007 Czechoslovak J.of Physics,v.43,p.783,1993, 4171400200008 ENDBIB 6 0 4171400200009 COMMON 4 3 4171400200010 EN-MIN EN-MAX E-MIN E-MAX 4171400200011 EV EV KEV KEV 4171400200012 0.2 230. 100. 1800. 4171400200013 ENDCOMMON 3 0 4171400200014 DATA 4 1 4171400200015 DATA 1DATA-ERR DATA 2DATA-ERR 2 4171400200016 PRT/FIS PRT/FIS MEV MEV 4171400200017 6.1 0.2 4.3 0.3 4171400200018 ENDDATA 3 0 4171400200019 ENDSUBENT 18 0 4171400299999 SUBENT 41714003 20201120 41914171400300001 BIB 6 15 4171400300002 REACTION 1(94-PU-239(N,F)0-G-0,PR,FY,,SPA) 4171400300003 2(94-PU-239(N,F)0-G-0,PR,KE,,SPA) 4171400300004 Energy of all gammas 4171400300005 ANALYSIS Directly measured values 6.1+-0.2 gammas/fis and 4171400300006 4.3+-0.3 MeV/fis ( gamma energy range 100 - 1800 keV) 4171400300007 were corrected for contribution of 1.8-10 MeV gammas by4171400300008 the data from V.V.Verbinski+. 4171400300009 MISC-COL (MISC) Energy of one gamma, MeV/fis. 4171400300010 INC-SPECT Resonance neutrons of 0.2 - 230. eV energy range. 4171400300011 REL-REF (A,,V.V.Verbinski+,J,PR/C,7,1173,1973) 4171400300012 Data for thermal neutrons. No significant difference. 4171400300013 STATUS (TABLE) Text pages 786-787 of 4171400300014 Czechoslovak J.of Physics,v.43,p.783,1993, 4171400300015 The same on page 1198 of Yad.Fiz.,v.57,is.7,p.1198,19944171400300016 (DEP,41714002) Directly measured data. 4171400300017 ENDBIB 15 0 4171400300018 COMMON 2 3 4171400300019 EN-MIN EN-MAX 4171400300020 EV EV 4171400300021 0.2 230. 4171400300022 ENDCOMMON 3 0 4171400300023 DATA 6 1 4171400300024 DATA 1DATA-ERR DATA 2DATA-ERR 2MISC MISC-ERR 4171400300025 PRT/FIS PRT/FIS MEV MEV SEE TEXT SEE TEXT 4171400300026 7.0 0.6 6.8 0.5 1.0 0.2 4171400300027 ENDDATA 3 0 4171400300028 ENDSUBENT 27 0 4171400399999 SUBENT 41714004 20201120 41914171400400001 BIB 5 17 4171400400002 REACTION (94-PU-239(N,F)ELEM/MASS,IND,FY,,SPA) 4171400400003 INC-SPECT Resonance neutrons in the energy range 0.2 - 230 eV, 4171400400004 spectrum is on Fig.1 of Yad.Fiz.,v.57,is.7,p.1198,19944171400400005 and Fig.2 of Czechoslovak J.of Physics,v.43,p.783,19934171400400006 MISC-COL (MISC) Gamma transition energy used to determine 4171400400007 fission yield. 4171400400008 FLAG (1.) 2+ -> 0+ transition 4171400400009 (2.) 3/2+ -> 1/2+ 4171400400010 (3.) 7/2+ -> 3/2+ 4171400400011 (4.) 6+ -> 4+ 4171400400012 (5.) 4+ -> 2+ 4171400400013 (6.) 3/2+ -> 7/2+ 4171400400014 (7.) 11/2+ -> 7/2+ 4171400400015 (8.) 8+ -> 6+ 4171400400016 STATUS (TABLE) Tables 1,2 of Yad.Fiz.,v.57,is.7,p.1198,1994 4171400400017 (COREL,41179003) Data for 290 nsec coincidence time 4171400400018 window. 4171400400019 ENDBIB 17 0 4171400400020 COMMON 2 3 4171400400021 EN-MIN EN-MAX 4171400400022 EV EV 4171400400023 0.2 230. 4171400400024 ENDCOMMON 3 0 4171400400025 DATA 6 40 4171400400026 ELEMENT MASS DATA DATA-ERR MISC FLAG 4171400400027 NO-DIM NO-DIM PC/FIS PC/FIS KEV NO-DIM 4171400400028 36. 88. 0.77 0.23 775. 1. 4171400400029 36. 90. 1.16 0.13 706. 1. 4171400400030 37. 93. 1.17 0.08 251. 4171400400031 38. 92. 0.78 0.17 814.7 1. 4171400400032 38. 94. 3.78 0.15 837.4 1. 4171400400033 38. 95. 2.79 0.13 351.9 2. 4171400400034 38. 95. 1.07 0.21 204.0 3. 4171400400035 38. 96. 1.38 0.11 815.0 1. 4171400400036 40. 98. 2.94 0.26 1223.0 1. 4171400400037 40. 100. 4.37 0.19 212.4 1. 4171400400038 40. 100. 1.48 0.13 497.0 4. 4171400400039 40. 102. 1.43 0.07 151.9 1. 4171400400040 42. 102. 1.70 0.18 296.0 1. 4171400400041 42. 104. 5.11 0.20 192.3 1. 4171400400042 42. 104. 4.03 0.18 368.7 5. 4171400400043 42. 104. 2.55 0.11 520.0 4. 4171400400044 42. 106. 2.24 0.09 171.7 1. 4171400400045 42. 106. 1.68 0.10 350.8 5. 4171400400046 50. 130. 0.92 0.29 1217.0 1. 4171400400047 50. 132. 2.46 0.10 973.9 1. 4171400400048 52. 134. 1.60 0.08 1279.8 1. 4171400400049 52. 134. 1.20 0.09 297.2 5. 4171400400050 52. 134. 0.93 0.16 706.0 8. 4171400400051 54. 136. 2.03 0.11 381.5 5. 4171400400052 54. 137. 3.99 0.22 601.0 6. 4171400400053 54. 138. 4.10 0.16 589.5 1. 4171400400054 54. 139. 2.65 0.28 571.2 7. 4171400400055 54. 140. 1.48 0.23 376.8 1. 4171400400056 54. 140. 1.11 0.11 457.9 5. 4171400400057 55. 140. 2.68 0.13 622.0 1. 4171400400058 56. 140. 0.97 0.30 602.3 1. 4171400400059 56. 142. 3.53 0.14 359.7 1. 4171400400060 56. 142. 2.78 0.12 475.7 5. 4171400400061 56. 142. 2.26 0.10 632.0 4. 4171400400062 56. 144. 3.24 0.13 199.4 1. 4171400400063 56. 144. 2.25 0.10 331.0 5. 4171400400064 56. 144. 1.50 0.07 431.7 4. 4171400400065 58. 146. 1.13 0.18 259.0 1. 4171400400066 58. 148. 1.01 0.36 158.7 1. 4171400400067 58. 148. 0.76 0.23 295.3 5. 4171400400068 ENDDATA 42 0 4171400400069 ENDSUBENT 68 0 4171400499999 ENDENTRY 4 0 4171499999999