ENTRY 41502 20201010 41934150200000001 SUBENT 41502001 20201010 41934150200100001 BIB 16 55 4150200100002 TITLE Prompt neutron emission in neutron-induced fission 4150200100003 of 239Pu and 235U 4150200100004 AUTHOR (O.A.Batenkov, G.A.Boykov, F.-J.Hambsch, J.H.Hamilton, 4150200100005 V.A.Jakovlev, V.A.Kalinin, A.B.Laptev, V.E.Sokolov, 4150200100006 A.S.Vorobyev) 4150200100007 REFERENCE (C,2004SANTA,1,1003,2004) 4150200100008 #doi:10.1063/1.1945175 4150200100009 INSTITUTE (4RUSLIN) A.B.Laptev, V.E.Sokolov, A.S.Vorob'ev 4150200100010 (A.S.Vorobiev=A.S.Vorobyev)4150200100011 (4RUSRI) O.A.Batenkov, G.A.Boykov, V.A.Jakovlev, 4150200100012 V.A.Kalinin 4150200100013 (2ZZZGEL) F.-J.Hambsch 4150200100014 (1USAVBT) J.H.Hamilton 4150200100015 (2JPNJNC) A.B.Laptev 4150200100016 FACILITY (REAC,4RUSLIN) WWR-M reactor of PNPI (Gatchina). 4150200100017 INC-SOURCE (REAC) Thermal neutron beam of WWR-M reactor. 4150200100018 METHOD (TOF) Time-of-flight technique for neutron velocities 4150200100019 determination. Time resolution about 2 ns. 4150200100020 (PHD) Mass dependent pulse height defect in gas mixture4150200100021 (PSD) Pulse shape discrimination technique to separate 4150200100022 prompt neutrons from gamma-rays. 4150200100023 DETECTOR (SCIN)Twelve stilbene crystals (NCD) of 5*3 cm, placed 4150200100024 at distance of about 50cm from fission chamber at 4150200100025 angles relative to normal of fission chamber cathode 4150200100026 plane: 0, 22, 57, 79, 79, 87, 95, 101, 101, 106, 146, 4150200100027 180 degrees. 4150200100028 For prompt neutrons accompanying fission detection. 4150200100029 Neutron registration threshold about 200 keV. 4150200100030 Neuron detection efficiency was determined in test 4150200100031 experiment with Cf-252 using the same set-up. 4150200100032 (IOCH) Ionization chamber for fission fragment kinetic 4150200100033 energy determination. 4150200100034 SAMPLE No information. 4150200100035 ANALYSIS For exp.data analysis the assumption that neutron 4150200100036 spectrum has Maxwell shape was used. 4150200100037 REL-REF (N,,G.Simon+,J,NIM/A,286,220,1990) -Method of fragment 4150200100038 angle determination. 4150200100039 (N,,O.Batenkov+,J,NIM/A,394,235,1997) -Pulse shape 4150200100040 discrimination technique. 4150200100041 (R,,W.Mannhart,R,IAEA-410,158,1987) -Reference standard4150200100042 spectrum, used in energy dependent detector efficiency4150200100043 determination. 4150200100044 ERR-ANALYS (ERR-S) Statistical error 4150200100045 Resolution of COS of angle about 0.07. 4150200100046 ADD-RES (ANGD) Fission fragment angular distributions measured 4150200100047 with IC. Neutron angular distributions 4150200100048 STATUS (PRELM) Preliminary data. 4150200100049 (TABLE) Data received from A.Vorobyev 06.02.2008 4150200100050 COMMENT -The work was made in framework of ISTC-554(2) project.4150200100051 HISTORY (20070831C) Compiled At CJD. M.M. 4150200100052 (20080206R) 4150200100053 (20111212A) Reaction was corrected in Subents 002-004 4150200100054 according to memo CP-D/701 (PFNS). 4150200100055 (20141105A) Reaction was corrected in Subents 002-004: 4150200100056 (20201010A) Subents 008,009,010 were corrected. 4150200100057 ENDBIB 55 0 4150200100058 NOCOMMON 0 0 4150200100059 ENDSUBENT 58 0 4150200199999 SUBENT 41502002 20141105 41654150200200001 BIB 7 33 4150200200002 REACTION ((92-U-235(N,F),PR,NU/DE,,MSC)/ 4150200200003 (98-CF-252(0,F),PR,NU/DE,,MSC)) 4150200200004 Dependence from E -prompt neutron energy in lab.system.4150200200005 See COMMENT for explanation of MSC. 4150200200006 INC-SPECT Neutron flux at target position about 1.E+7 n/s/cm**2.4150200200007 EN-SEC (E,N) Prompt neutron energy. 4150200200008 ADD-RES Formula (1) in the article 4150200200009 R(E)=((Tcf/Tu5)**1.5)*exp(-(Tcf-Tu5)/(TCf*Tu5)), 4150200200010 was used in fitting, 4150200200011 where Tcf, Tu5 -spectrum temperature for Cf and U-235.4150200200012 Tcf=1.42 MeV was used, 4150200200013 Tu5 was defined to be 1.31 MeV ( preliminary value). 4150200200014 COMMENT Of Roberto Capote (2014-10-23): 4150200200015 The temperature quoted in the article (1.31 MeV for 4150200200016 235U) does not reproduce the calculated ratio in Fig.5 4150200200017 (top) well. 4150200200018 Better agreement is seen by changing it to 1.29 MeV. 4150200200019 Best fitting was obtained by formula: 4150200200020 -E/1.2876+E/1.42+0.70598 , 4150200200021 using DATA of energy range 0.5-5 MeV. 4150200200022 - Of author A.S.Vorobyev 06.11.2014 4150200200023 Subents 002-004: plots were prepared in RI institute, 4150200200024 probably log (or ln) was implemented for scale Y. 4150200200025 Futher analysis could be applied. 4150200200026 STATUS Data are presented on Fig.5 - top. 4150200200027 HISTORY (20111212A) 4150200200028 (92-U-235(N,F),PR,DE,N)/(98-CF-252(N,F),PR,DE,N) -> 4150200200029 (92-U-235(N,F),PR,NU/DE)/(98-CF-252(N,0),PR,NU/DE) 4150200200030 (20141105A) PR,NU/DE -> PR/NU/DE,,MSC according to the 4150200200031 request of NDS,IAEA - see explanation in COMMENT of 4150200200032 Roberto Capote in Subent 002. 4150200200033 NO-DIM -> ARB-UNITS. 4150200200034 Comment of author was added . 4150200200035 ENDBIB 33 0 4150200200036 COMMON 1 3 4150200200037 EN-DUMMY 4150200200038 EV 4150200200039 0.0253 4150200200040 ENDCOMMON 3 0 4150200200041 DATA 3 63 4150200200042 E DATA ERR-S 4150200200043 MEV ARB-UNITS ARB-UNITS 4150200200044 0.12 0.22659 0.27651 4150200200045 0.145 0.70621 0.23425 4150200200046 0.175 0.78953 0.19025 4150200200047 0.205 0.65208 0.11105 4150200200048 0.235 0.75599 0.09332 4150200200049 0.275 0.72271 0.05455 4150200200050 0.325 0.80807 0.05087 4150200200051 0.375 0.73923 0.04212 4150200200052 0.425 0.77347 0.04179 4150200200053 0.475 0.69772 0.03697 4150200200054 0.525 0.73789 0.03914 4150200200055 0.575 0.68646 0.03545 4150200200056 0.625 0.68406 0.03497 4150200200057 0.675 0.68658 0.03466 4150200200058 0.725 0.67254 0.03427 4150200200059 0.775 0.70867 0.03589 4150200200060 0.825 0.65016 0.03339 4150200200061 0.875 0.67006 0.03533 4150200200062 0.925 0.625 0.03341 4150200200063 0.975 0.67542 0.03575 4150200200064 1.05 0.61426 0.02343 4150200200065 1.15 0.6204 0.0245 4150200200066 1.25 0.62843 0.02557 4150200200067 1.35 0.59291 0.02442 4150200200068 1.45 0.58923 0.02576 4150200200069 1.55 0.57261 0.02551 4150200200070 1.65 0.53966 0.02412 4150200200071 1.75 0.54748 0.02595 4150200200072 1.85 0.553 0.02682 4150200200073 2.0 0.52997 0.01934 4150200200074 2.2 0.55431 0.02105 4150200200075 2.4 0.55377 0.02239 4150200200076 2.6 0.51703 0.02265 4150200200077 2.8 0.51599 0.02444 4150200200078 3.05 0.48412 0.02098 4150200200079 3.35 0.45833 0.02228 4150200200080 3.65 0.43269 0.0236 4150200200081 3.95 0.42013 0.02648 4150200200082 4.25 0.37632 0.02631 4150200200083 4.55 0.43535 0.03383 4150200200084 4.85 0.41345 0.03718 4150200200085 5.25 0.40914 0.03343 4150200200086 5.75 0.3592 0.03645 4150200200087 6.25 0.37677 0.04639 4150200200088 6.75 0.35742 0.05611 4150200200089 7.25 0.3422 0.06621 4150200200090 7.75 0.34735 0.0826 4150200200091 8.25 0.42339 0.12198 4150200200092 8.75 0.5378 0.18393 4150200200093 9.25 0.37213 0.17265 4150200200094 9.75 0.40626 0.18817 4150200200095 10.25 0.65052 0.42306 4150200200096 10.75 0.51242 0.4273 4150200200097 11.25 0.23117 0.22445 4150200200098 11.75 0.27242 0.33048 4150200200099 12.25 0.26826 0.51296 4150200200100 12.75 0.67622 2.29316 4150200200101 13.25 1.52247 3.79709 4150200200102 13.75 1.00824 3.92296 4150200200103 14.75 0.53555 1.2514 4150200200104 15.5 1.4328 5.1731 4150200200105 16.5 0.12391 0.86042 4150200200106 17.5 0.96083 5.06185 4150200200107 ENDDATA 65 0 4150200200108 ENDSUBENT 107 0 4150200299999 SUBENT 41502003 20141105 41654150200300001 BIB 7 25 4150200300002 REACTION ((94-PU-239(N,F),PR,NU/DE,,MSC)/ 4150200300003 (98-CF-252(0,F),PR,NU/DE,,MSC)) 4150200300004 Dependence from E -prompt neutron energy in lab.system.4150200300005 See COMMENT for explanation of MSC. 4150200300006 INC-SPECT Neutron flux at target position about 1.E+7 n/s/cm**2.4150200300007 EN-SEC (E,N) Prompt neutron energy. 4150200300008 ADD-RES Formula (1) in the article 4150200300009 R(E)=((Tcf/Tpu)**1.5)*exp(-(Tcf-Tpu5/(TCf*Tpu)), 4150200300010 was used in fitting, 4150200300011 where Tcf, Tpu -spectrum temperature for Cf and Pu-2394150200300012 Tcf=1.42 MeV was used, 4150200300013 Tpu was defined to be 1.36 MeV ( preliminary value). 4150200300014 COMMENT - Of author A.S.Vorobyev 06.11.2014 4150200300015 Subents 002-004: plots were prepared in RI institute, 4150200300016 probably log (or ln) was implemented for scale Y. 4150200300017 Futher analysis could be applied. 4150200300018 STATUS Data are presented on Fig.5 - middle. 4150200300019 HISTORY (20111212A) 4150200300020 (94-PU-239(N,F),PR,DE,N)/(98-CF-252(N,F),PR,DE,N) -> 4150200300021 (94-PU-239(N,F),PR,NU/DE)/(98-CF-252(N,0),PR,NU/DE) 4150200300022 (20141105A) PR,NU/DE -> PR/NU/DE,,MSC according to the 4150200300023 request of NDS,IAEA - see explanation in COMMENT of 4150200300024 Roberto Capote in Subent 002. 4150200300025 NO-DIM -> ARB-UNITS. 4150200300026 Comment of author was added . 4150200300027 ENDBIB 25 0 4150200300028 COMMON 1 3 4150200300029 EN-DUMMY 4150200300030 EV 4150200300031 0.0253 4150200300032 ENDCOMMON 3 0 4150200300033 DATA 3 63 4150200300034 E DATA ERR-S 4150200300035 MEV ARB-UNITS ARB-UNITS 4150200300036 0.12 0.5821 0.44882 4150200300037 0.145 0.79541 0.27945 4150200300038 0.175 0.93906 0.21079 4150200300039 0.205 0.86294 0.12647 4150200300040 0.235 0.81531 0.09708 4150200300041 0.275 0.83907 0.06129 4150200300042 0.325 0.78206 0.04755 4150200300043 0.375 0.74575 0.04174 4150200300044 0.425 0.71814 0.03872 4150200300045 0.475 0.74834 0.03819 4150200300046 0.525 0.74751 0.03831 4150200300047 0.575 0.66794 0.03377 4150200300048 0.625 0.70282 0.03469 4150200300049 0.675 0.70483 0.0344 4150200300050 0.725 0.71694 0.03542 4150200300051 0.775 0.69669 0.03422 4150200300052 0.825 0.6959 0.03465 4150200300053 0.875 0.71669 0.03585 4150200300054 0.925 0.6751 0.03413 4150200300055 0.975 0.71554 0.03613 4150200300056 1.05 0.6741 0.02444 4150200300057 1.15 0.69082 0.02599 4150200300058 1.25 0.68661 0.02638 4150200300059 1.35 0.67286 0.02618 4150200300060 1.45 0.67969 0.0275 4150200300061 1.55 0.6755 0.02788 4150200300062 1.65 0.62196 0.02621 4150200300063 1.75 0.68162 0.02963 4150200300064 1.85 0.6266 0.02844 4150200300065 2.0 0.63455 0.02144 4150200300066 2.2 0.66458 0.02337 4150200300067 2.4 0.64202 0.02425 4150200300068 2.6 0.62622 0.02547 4150200300069 2.8 0.60292 0.02684 4150200300070 3.05 0.61402 0.0245 4150200300071 3.35 0.59018 0.02632 4150200300072 3.65 0.55808 0.02826 4150200300073 3.95 0.57856 0.03321 4150200300074 4.25 0.50898 0.03315 4150200300075 4.55 0.50868 0.03817 4150200300076 4.85 0.52555 0.04355 4150200300077 5.25 0.51118 0.0387 4150200300078 5.75 0.48099 0.04484 4150200300079 6.25 0.44522 0.05255 4150200300080 6.75 0.43487 0.06368 4150200300081 7.25 0.51571 0.08653 4150200300082 7.75 0.46346 0.10063 4150200300083 8.25 0.48566 0.13339 4150200300084 8.75 0.44076 0.16579 4150200300085 9.25 0.41915 0.16801 4150200300086 9.75 0.31019 0.16145 4150200300087 10.25 0.66601 0.39136 4150200300088 10.75 0.43798 0.38458 4150200300089 11.25 0.07002 0.19368 4150200300090 12.75 0.59291 1.15625 4150200300091 13.25 0.30574 1.32401 4150200300092 13.75 0.31997 1.36943 4150200300093 14.25 0.52298 1.66117 4150200300094 14.75 0.16647 0.68041 4150200300095 15.5 0.14575 1.41717 4150200300096 16.5 0.22083 0.97276 4150200300097 18.5 0.06368 5.49468 4150200300098 19.5 0.28172 2.19021 4150200300099 ENDDATA 65 0 4150200300100 ENDSUBENT 99 0 4150200399999 SUBENT 41502004 20141105 41654150200400001 BIB 7 27 4150200400002 REACTION ((94-PU-239(N,F),PR,NU/DE,,MSC)/ 4150200400003 (98-CF-252(0,F),PR,NU/DE,,MSC)) 4150200400004 Dependence from E -prompt neutron energy in lab.system.4150200400005 See COMMENT for explanation of MSC. 4150200400006 INC-SPECT Strong resonance at 0.296 eV was selected by Sm filter.4150200400007 Admixture of thermal neutrons - less 5%, 4150200400008 of neutrons of higher energy - less 10%. 4150200400009 EN-SEC (E,N) Prompt neutron energy. 4150200400010 ADD-RES Formula (1) in the article 4150200400011 R(E)=((Tcf/Tpu)**1.5)*exp(-(Tcf-Tpu)/(TCf*Tpu)), 4150200400012 was used in fitting, 4150200400013 where Tcf, Tpu -spectrum temperature for Cf and Pu-2394150200400014 Tcf=1.42 MeV was used, 4150200400015 Tpu was defined to be 1.37 MeV ( preliminary value). 4150200400016 COMMENT - Of author A.S.Vorobyev 06.11.2014 4150200400017 Subents 002-004: plots were prepared in RI institute, 4150200400018 probably log (or ln) was implemented for scale Y. 4150200400019 Futher analysis could be applied. 4150200400020 STATUS Data are presented on Fig.5 - bottom. 4150200400021 HISTORY (20111212A) 4150200400022 (94-PU-239(N,F),PR,DE,N)/(98-CF-252(N,F),PR,DE,N) -> 4150200400023 (94-PU-239(N,F),PR,NU/DE)/(98-CF-252(N,0),PR,NU/DE) 4150200400024 (20141105A) PR,NU/DE -> PR/NU/DE,,MSC according to the 4150200400025 request of NDS,IAEA - see explanation in COMMENT of 4150200400026 Roberto Capote in Subent 002. 4150200400027 NO-DIM -> ARB-UNITS. 4150200400028 Comment of author was added . 4150200400029 ENDBIB 27 0 4150200400030 COMMON 1 3 4150200400031 EN 4150200400032 EV 4150200400033 0.296 4150200400034 ENDCOMMON 3 0 4150200400035 DATA 3 58 4150200400036 E DATA ERR-S 4150200400037 MEV ARB-UNITS ARB-UNITS 4150200400038 0.12 0.24305 0.34906 4150200400039 0.145 0.74497 0.21466 4150200400040 0.175 0.98019 0.16779 4150200400041 0.205 0.73588 0.12427 4150200400042 0.235 0.68027 0.10406 4150200400043 0.275 0.5985 0.06545 4150200400044 0.325 0.70419 0.06159 4150200400045 0.375 0.77985 0.05942 4150200400046 0.425 0.73962 0.05596 4150200400047 0.475 0.72013 0.05356 4150200400048 0.525 0.68093 0.05142 4150200400049 0.575 0.70947 0.05173 4150200400050 0.625 0.70956 0.05135 4150200400051 0.675 0.7024 0.05127 4150200400052 0.725 0.65869 0.04967 4150200400053 0.775 0.65853 0.04982 4150200400054 0.825 0.7154 0.05208 4150200400055 0.875 0.67872 0.0512 4150200400056 0.925 0.60225 0.04871 4150200400057 0.975 0.67661 0.05215 4150200400058 1.05 0.70628 0.0382 4150200400059 1.15 0.61741 0.03641 4150200400060 1.25 0.60539 0.03689 4150200400061 1.35 0.66594 0.03952 4150200400062 1.45 0.66186 0.04037 4150200400063 1.55 0.70882 0.04313 4150200400064 1.65 0.70257 0.04421 4150200400065 1.75 0.65106 0.0437 4150200400066 1.85 0.6677 0.04572 4150200400067 2.0 0.62688 0.03285 4150200400068 2.2 0.66291 0.03589 4150200400069 2.4 0.62775 0.03743 4150200400070 2.6 0.64672 0.04077 4150200400071 2.8 0.62044 0.04318 4150200400072 3.05 0.59802 0.03779 4150200400073 3.35 0.5374 0.04017 4150200400074 3.65 0.53107 0.04483 4150200400075 3.95 0.60899 0.05426 4150200400076 4.25 0.46442 0.05354 4150200400077 4.55 0.52403 0.0644 4150200400078 4.85 0.60084 0.0775 4150200400079 5.25 0.51124 0.06502 4150200400080 5.75 0.61991 0.08829 4150200400081 6.25 0.53838 0.10185 4150200400082 6.75 0.42017 0.11393 4150200400083 7.25 0.43768 0.14495 4150200400084 7.75 0.42531 0.17907 4150200400085 8.25 0.22486 0.19121 4150200400086 8.75 0.56477 0.30648 4150200400087 9.25 0.65131 0.40786 4150200400088 9.75 0.35312 0.45963 4150200400089 10.25 0.08092 0.50235 4150200400090 10.75 0.55073 0.79387 4150200400091 11.25 0.30203 0.89713 4150200400092 11.75 0.50335 1.11709 4150200400093 12.25 2.16639 2.01679 4150200400094 12.75 1.14149 2.15739 4150200400095 14.75 0.72386 4.89568 4150200400096 ENDDATA 60 0 4150200400097 ENDSUBENT 96 0 4150200499999 SUBENT 41502005 20070831 41424150200500001 BIB 2 4 4150200500002 REACTION (92-U-235(N,F)MASS,PR,NU) 4150200500003 Average neutron multiplicity as dependence from 4150200500004 preneutron fragment mass 4150200500005 STATUS Fig.6 - top. 4150200500006 ENDBIB 4 0 4150200500007 COMMON 1 3 4150200500008 EN-DUMMY 4150200500009 EV 4150200500010 0.0253 4150200500011 ENDCOMMON 3 0 4150200500012 DATA 3 21 4150200500013 MASS DATA ERR-S 4150200500014 NO-DIM PRT/FIS PRT/FIS 4150200500015 81. 0.101 0.08 4150200500016 85. 0.38461 0.06226 4150200500017 89. 0.86921 0.07967 4150200500018 93. 1.08352 0.05528 4150200500019 97. 1.47253 0.05353 4150200500020 101. 1.72239 0.0537 4150200500021 105. 1.89325 0.0625 4150200500022 109. 2.10817 0.08915 4150200500023 113. 2.9817 0.21802 4150200500024 117. 3.05699 0.55837 4150200500025 121. 0.35537 0.0948 4150200500026 125. 0.16124 0.02606 4150200500027 129. 0.61656 0.04687 4150200500028 133. 0.77552 0.0409 4150200500029 137. 0.92802 0.03875 4150200500030 141. 1.18468 0.04419 4150200500031 145. 1.3347 0.05932 4150200500032 149. 1.52529 0.09784 4150200500033 153. 2.21477 0.25219 4150200500034 157. 1.82127 0.42385 4150200500035 161. 1.488 0.824 4150200500036 ENDDATA 23 0 4150200500037 ENDSUBENT 36 0 4150200599999 SUBENT 41502006 20070831 41424150200600001 BIB 2 4 4150200600002 REACTION (94-PU-239(N,F)MASS,PR,NU) 4150200600003 Average neutron multiplicity as dependence from 4150200600004 preneutron fragment mass 4150200600005 STATUS Fig.6 - bottom. 4150200600006 ENDBIB 4 0 4150200600007 COMMON 1 3 4150200600008 EN-DUMMY 4150200600009 EV 4150200600010 0.0253 4150200600011 ENDCOMMON 3 0 4150200600012 DATA 3 21 4150200600013 MASS DATA ERR-S 4150200600014 NO-DIM PRT/FIS PRT/FIS 4150200600015 85. 0.75967 0.27869 4150200600016 89. 0.62593 0.09438 4150200600017 93. 0.79335 0.07141 4150200600018 97. 1.21424 0.0572 4150200600019 101. 1.27896 0.05176 4150200600020 105. 1.53927 0.05727 4150200600021 109. 2.40176 0.09399 4150200600022 113. 2.97704 0.2109 4150200600023 117. 4.43992 0.67747 4150200600024 121. 1.84936 0.63145 4150200600025 125. 0.21571 0.08666 4150200600026 129. 0.47203 0.05106 4150200600027 133. 0.65661 0.0432 4150200600028 137. 1.1116 0.04859 4150200600029 141. 1.34473 0.0527 4150200600030 145. 1.53146 0.06469 4150200600031 149. 1.73093 0.10293 4150200600032 153. 1.6986 0.1632 4150200600033 157. 2.50675 0.39422 4150200600034 161. 4.06332 1.11584 4150200600035 165. 2.089 1.74 4150200600036 ENDDATA 23 0 4150200600037 ENDSUBENT 36 0 4150200699999 SUBENT 41502007 20070831 41424150200700001 BIB 3 9 4150200700002 REACTION (94-PU-239(N,F)MASS,PR,NU) 4150200700003 Average neutron multiplicity as dependence from 4150200700004 preneutron fragment mass. 4150200700005 INC-SPECT For fragment-neutron correlation measurement on Pu 4150200700006 target the region of strong resonance at 0.296 eV was4150200700007 selected by Sm filter, arranged in the flux from 4150200700008 reactor. Admixture of thermal neutrons less 5% and 4150200700009 of neutrons of higher energies less 10%. 4150200700010 STATUS Fig.6 - bottom. 4150200700011 ENDBIB 9 0 4150200700012 COMMON 1 3 4150200700013 EN 4150200700014 EV 4150200700015 0.296 4150200700016 ENDCOMMON 3 0 4150200700017 DATA 3 19 4150200700018 MASS DATA ERR-S 4150200700019 NO-DIM PRT/FIS PRT/FIS 4150200700020 85. 1.86474 1.34608 4150200700021 89. 0.51374 0.21695 4150200700022 93. 0.60726 0.18685 4150200700023 97. 1.05605 0.14774 4150200700024 101. 1.65469 0.12398 4150200700025 105. 1.86641 0.18797 4150200700026 109. 2.48361 0.21635 4150200700027 113. 3.28512 0.42418 4150200700028 117. 4.66351 0.25167 4150200700029 121. 5.0789 3.03608 4150200700030 125. 1.04513 0.56919 4150200700031 129. 0.05563 0.02167 4150200700032 133. 1.07585 0.16385 4150200700033 137. 1.089 0.09515 4150200700034 141. 1.55121 0.1334 4150200700035 145. 1.48518 0.173 4150200700036 149. 1.43229 0.25597 4150200700037 153. 1.68363 0.64682 4150200700038 157. 4.95761 4.57351 4150200700039 ENDDATA 21 0 4150200700040 ENDSUBENT 39 0 4150200799999 SUBENT 41502008 20201010 41934150200800001 BIB 3 6 4150200800002 REACTION (92-U-235(N,F)MASS,PR,KE,N) 4150200800003 Average prompt neutron energy as dependence from 4150200800004 preneutron fragment mass in fragment center of mass 4150200800005 system. 4150200800006 STATUS Fig.7 - top. 4150200800007 HISTORY (20201010A) Reaction was corrected AKE -> KE 4150200800008 ENDBIB 6 0 4150200800009 COMMON 1 3 4150200800010 EN-DUMMY 4150200800011 EV 4150200800012 0.0253 4150200800013 ENDCOMMON 3 0 4150200800014 DATA 3 21 4150200800015 MASS DATA-CM ERR-S 4150200800016 NO-DIM MEV MEV 4150200800017 81. 0.49 0.51 4150200800018 85. 1.13571 0.28598 4150200800019 89. 1.07525 0.17492 4150200800020 93. 1.01893 0.09477 4150200800021 97. 1.28674 0.08069 4150200800022 101. 1.22174 0.06748 4150200800023 105. 1.32488 0.07809 4150200800024 109. 1.36565 0.10429 4150200800025 113. 1.34295 0.17541 4150200800026 117. 0.95928 0.27304 4150200800027 121. 0.90 0.37 4150200800028 125. 0.80572 0.20234 4150200800029 129. 1.71274 0.20447 4150200800030 133. 1.29707 0.13246 4150200800031 137. 1.24797 0.09997 4150200800032 141. 1.18624 0.08269 4150200800033 145. 1.07938 0.09758 4150200800034 149. 1.11088 0.13315 4150200800035 153. 1.18896 0.23765 4150200800036 157. 0.44989 0.15074 4150200800037 161. 0.097 0.072 4150200800038 ENDDATA 23 0 4150200800039 ENDSUBENT 38 0 4150200899999 SUBENT 41502009 20201010 41934150200900001 BIB 3 6 4150200900002 REACTION (94-PU-239(N,F)MASS,PR,KE,N) 4150200900003 Average prompt neutron energy as dependence from 4150200900004 preneutron fragment mass in fragment center of mass 4150200900005 system. 4150200900006 STATUS Fig.7 - bottom. 4150200900007 HISTORY (20201010A) Reaction was corrected AKE -> KE 4150200900008 ENDBIB 6 0 4150200900009 COMMON 1 3 4150200900010 EN-DUMMY 4150200900011 EV 4150200900012 0.0253 4150200900013 ENDCOMMON 3 0 4150200900014 DATA 3 21 4150200900015 MASS DATA ERR-S 4150200900016 NO-DIM MEV MEV 4150200900017 85. 1.43849 0.7997 4150200900018 89. 0.97645 0.20883 4150200900019 93. 0.8938 0.1337 4150200900020 97. 1.37891 0.10095 4150200900021 101. 1.30836 0.09226 4150200900022 105. 1.23454 0.07897 4150200900023 109. 1.73512 0.10904 4150200900024 113. 1.50699 0.18594 4150200900025 117. 1.39831 0.35615 4150200900026 121. 1.68581 0.81265 4150200900027 125. 0.33347 0.15539 4150200900028 129. 1.6675 0.26586 4150200900029 133. 1.27264 0.15304 4150200900030 137. 1.67022 0.13099 4150200900031 141. 1.42163 0.09888 4150200900032 145. 1.32625 0.10359 4150200900033 149. 1.23117 0.12165 4150200900034 153. 1.02268 0.17991 4150200900035 157. 1.36975 0.34916 4150200900036 161. 1.13268 0.50767 4150200900037 165. 0.115 0.127 4150200900038 ENDDATA 23 0 4150200900039 ENDSUBENT 38 0 4150200999999 SUBENT 41502010 20201010 41934150201000001 BIB 4 11 4150201000002 REACTION (94-PU-239(N,F)MASS,PR,KE,N) 4150201000003 Average prompt neutron energy as dependence from 4150201000004 preneutron fragment mass in fragment center of mass 4150201000005 system. 4150201000006 INC-SPECT For fragment-neutron correlation measurement on Pu 4150201000007 target the region of strong resonance at 0.296 eV was4150201000008 selected by Sm filter, arranged in the flux from 4150201000009 reactor. Admixture of thermal neutrons less 5% and 4150201000010 of neutrons of higher energies less 10%. 4150201000011 STATUS Fig.7 - bottom. 4150201000012 HISTORY (20201010A) Reaction was corrected AKE -> KE 4150201000013 ENDBIB 11 0 4150201000014 COMMON 1 3 4150201000015 EN 4150201000016 EV 4150201000017 0.296 4150201000018 ENDCOMMON 3 0 4150201000019 DATA 3 18 4150201000020 MASS DATA ERR-S 4150201000021 NO-DIM MEV MEV 4150201000022 85. 0.55 0.55 4150201000023 89. 0.8 0.5 4150201000024 93. 1.07657 0.42756 4150201000025 97. 1.10125 0.20537 4150201000026 101. 1.09881 0.12764 4150201000027 105. 1.50682 0.31155 4150201000028 109. 1.37818 0.21562 4150201000029 113. 1.20342 0.23873 4150201000030 117. 1.28381 0.37138 4150201000031 121. 1.4 1.0 4150201000032 125. 1.5 1.2 4150201000033 129. 1.22934 0.52297 4150201000034 133. 1.92733 0.60566 4150201000035 137. 1.11177 0.16544 4150201000036 141. 1.2145 0.18483 4150201000037 145. 0.9098 0.1793 4150201000038 149. 0.64482 0.15937 4150201000039 153. 0.85589 0.44502 4150201000040 ENDDATA 20 0 4150201000041 ENDSUBENT 40 0 4150201099999 ENDENTRY 10 0 4150299999999