ENTRY 14290 20190529 14521429000000001 SUBENT 14290001 20190529 14521429000100001 BIB 12 51 1429000100002 TITLE Prompt fission neutron spectra from fission induced 1429000100003 by 1 to 8 MeV neutrons on 235U and 239Pu using the 1429000100004 double time-of-flight technique 1429000100005 AUTHOR (S.Noda, R.C.Haight, R.O.Nelson, M.Devlin, 1429000100006 J.M.O'Donnell, A.Chatillon, T.Granier, G.Belier, 1429000100007 J.Taieb, T.Kawano, P.Talou) 1429000100008 INSTITUTE (1USALAS,2FR BRC) 1429000100009 REFERENCE (J,PR/C,83,034604,2011) 1429000100010 #doi:10.1103/PhysRevC.83.034604 1429000100011 #NSR: 2011NO02 1429000100012 (J,KPS,59,1553,2011) 1429000100013 #doi:10.3938/jkps.59.1553 1429000100014 #NSR: 2011HA54 1429000100015 FACILITY (LINAC,1USALAS) Weapons Neutron Research facility 1429000100016 (WNR) of the Los Alamos Neutron Science Center 1429000100017 INC-SOURCE (SPALL) The incident neutron beam at WNR is produced 1429000100018 by the 800 MeV proton beam, bunched to 200 ps, 1429000100019 striking a tungsten target. 1429000100020 DETECTOR (FISCH) Multiplate fission ionization chamber 1429000100021 fabricated by CEA contained the target materials 1429000100022 (SCIN) FIGARO array of 20 neutron detectors was used 1429000100023 to detect the fission neutrons. 1429000100024 These detectors were Eljen EJ301 liquid organic 1429000100025 scintillators, 12.5 cm in diameter and 5 cm thick, 1429000100026 each being viewed by a Hamamatsu R1250A 5 inch 1429000100027 photomultiplier tube. 1429000100028 (BAF2) Gamma ray output from fission events was 1429000100029 investigated with a BaF2 scintillator located at 1429000100030 90deg relative to the beam direction 1429000100031 METHOD (TOF) Time of flight method was used to determine 1429000100032 the energy of incident neutrons from WNR facility as 1429000100033 well as for energy of fission neutrons. 1429000100034 The flight path from WNR spallation target to 1429000100035 actinide sample was 22.74 m, the flight path for 1429000100036 fission neutrons from sample to neutron detector was 1429000100037 1 m. 1429000100038 CORRECTION Not corrected for scattering of the fission neutrons 1429000100039 from components of the fission chamber. 1429000100040 Monte Carlo calculations show the measurement is 1429000100041 predicted to be 6% lower than the unscattered spectrum1429000100042 at 5 MeV and 7% lower at 8 MeV relative to the yield 1429000100043 at 2 MeV. 1429000100044 ERR-ANALYS Detector efficiencies believed to be accurate to about 1429000100045 5% (somewhat higher near the detection threshold) are 1429000100046 not included in uncertainty values given. 1429000100047 STATUS (APRVD) Approved by Shusaku Noda (2011-10-06) 1429000100048 HISTORY (20110315C) Compiled by S.H. 1429000100049 (20110830R) On. Data received from Shusaku Noda 1429000100050 (20111005A) On. BIB updated 1429000100051 (20190529A) OG. 2nd ref. added. #NSR and #doi added. 1429000100052 Sub007 added. 1429000100053 ENDBIB 51 0 1429000100054 NOCOMMON 0 0 1429000100055 ENDSUBENT 54 0 1429000199999 SUBENT 14290002 20111006 13731429000200001 BIB 3 7 1429000200002 REACTION (92-U-235(N,F),PR,NU/DE,,AV/REL) 1429000200003 Spectra are normalized to unity by integrating the 1429000200004 spectra in the 2.0-6.5 MeV emission energy range 1429000200005 ERR-ANALYS (ERR-S) Statistical uncertainty, considering 1429000200006 - foregound counting statistics (Poisson) 1429000200007 - background counting statistics (Gaussian) 1429000200008 STATUS (TABLE) Plotted in Fig.7 of Phys.Rev.C83(2011)034604 1429000200009 ENDBIB 7 0 1429000200010 NOCOMMON 0 0 1429000200011 DATA 6 63 1429000200012 EN-MIN EN-MAX E DATA -ERR-S +ERR-S 1429000200013 MEV MEV MEV ARB-UNITS ARB-UNITS ARB-UNITS 1429000200014 1. 2. 1.5 7.6634E-01 3.4578E-01 2.9948E-011429000200015 1. 2. 2.5 5.1220E-01 1.9031E-01 1.6367E-011429000200016 1. 2. 3.5 2.7136E-01 4.7978E-02 4.5734E-021429000200017 1. 2. 4.5 1.3310E-01 1.1420E-02 2.1800E-021429000200018 1. 2. 5.5 7.5068E-02 8.7619E-03 1.9148E-021429000200019 1. 2. 6.5 3.3144E-02 6.0276E-03 1.4288E-021429000200020 1. 2. 7.5 2.9787E-02 5.9503E-03 1.4842E-021429000200021 1. 2. 8.5 2.1380E-02 5.1812E-03 1.2143E-021429000200022 1. 2. 9.5 1.3994E-02 4.2400E-03 9.5915E-031429000200023 2. 3. 1.5 8.3934E-01 3.6996E-01 3.2672E-011429000200024 2. 3. 2.5 4.8540E-01 2.2839E-01 1.6388E-011429000200025 2. 3. 3.5 2.8369E-01 4.2861E-02 4.2887E-021429000200026 2. 3. 4.5 1.5099E-01 1.5476E-02 2.7254E-021429000200027 2. 3. 5.5 6.8969E-02 9.4327E-03 2.1264E-021429000200028 2. 3. 6.5 4.3822E-02 7.7132E-03 1.9475E-021429000200029 2. 3. 7.5 3.2996E-02 6.8538E-03 1.6179E-021429000200030 2. 3. 8.5 3.0514E-02 6.6570E-03 1.6481E-021429000200031 2. 3. 9.5 1.7097E-02 5.2949E-03 1.4177E-021429000200032 3. 4. 1.5 7.8938E-01 2.8546E-01 2.5160E-011429000200033 3. 4. 2.5 4.8192E-01 1.9449E-01 1.4643E-011429000200034 3. 4. 3.5 2.8050E-01 4.8526E-02 4.7933E-021429000200035 3. 4. 4.5 1.2780E-01 1.5021E-02 3.2572E-021429000200036 3. 4. 5.5 9.7759E-02 1.2573E-02 2.8864E-021429000200037 3. 4. 6.5 4.8078E-02 8.7724E-03 2.1717E-021429000200038 3. 4. 7.5 2.9722E-02 7.1501E-03 1.9729E-021429000200039 3. 4. 8.5 2.5483E-02 6.9822E-03 1.6570E-021429000200040 3. 4. 9.5 2.2492E-02 9.1229E-03 1.6599E-021429000200041 4. 5. 1.5 7.8988E-01 2.7363E-01 2.3985E-011429000200042 4. 5. 2.5 4.9132E-01 9.0567E-02 8.4779E-021429000200043 4. 5. 3.5 2.7111E-01 3.4510E-02 4.8395E-021429000200044 4. 5. 4.5 1.7023E-01 1.7843E-02 3.9483E-021429000200045 4. 5. 5.5 5.6751E-02 1.0347E-02 2.7475E-021429000200046 4. 5. 6.5 4.2373E-02 9.2886E-03 2.4634E-021429000200047 4. 5. 7.5 4.2313E-02 9.9545E-03 2.5817E-021429000200048 4. 5. 8.5 2.9175E-02 8.5234E-03 1.9648E-021429000200049 4. 5. 9.5 1.5063E-02 6.1665E-03 1.7061E-021429000200050 5. 6. 1.5 6.6193E-01 1.6258E-01 1.5520E-011429000200051 5. 6. 2.5 4.7825E-01 7.6196E-02 7.4723E-021429000200052 5. 6. 3.5 2.7520E-01 3.6162E-02 5.2546E-021429000200053 5. 6. 4.5 1.3590E-01 1.6310E-02 3.8609E-021429000200054 5. 6. 5.5 9.6676E-02 1.7083E-02 3.5585E-021429000200055 5. 6. 6.5 5.5864E-02 1.0853E-02 2.9867E-021429000200056 5. 6. 7.5 6.0074E-02 1.2300E-02 2.9232E-021429000200057 5. 6. 8.5 2.0400E-02 6.7520E-03 1.7905E-021429000200058 5. 6. 9.5 2.0885E-02 9.1853E-03 1.9488E-021429000200059 6. 7. 1.5 8.4008E-01 2.6385E-01 2.2882E-011429000200060 6. 7. 2.5 4.8478E-01 1.4817E-01 1.2665E-011429000200061 6. 7. 3.5 2.8010E-01 3.1774E-02 5.1972E-021429000200062 6. 7. 4.5 1.5668E-01 2.0127E-02 4.2868E-021429000200063 6. 7. 5.5 6.5305E-02 1.2469E-02 3.0465E-021429000200064 6. 7. 6.5 5.2547E-02 1.1624E-02 3.0433E-021429000200065 6. 7. 7.5 2.7719E-02 8.0110E-03 2.2166E-021429000200066 6. 7. 8.5 2.9449E-02 9.1396E-03 2.3718E-021429000200067 6. 7. 9.5 1.7917E-02 6.9746E-03 1.9266E-021429000200068 7. 8. 1.5 7.7380E-01 2.0130E-01 1.8235E-011429000200069 7. 8. 2.5 4.8374E-01 7.0538E-02 7.3822E-021429000200070 7. 8. 3.5 2.4631E-01 3.9625E-02 5.5819E-021429000200071 7. 8. 4.5 1.3620E-01 1.7719E-02 4.2830E-021429000200072 7. 8. 5.5 1.2387E-01 2.2123E-02 4.2851E-021429000200073 7. 8. 6.5 3.9496E-02 9.5679E-03 2.4914E-021429000200074 7. 8. 7.5 3.5863E-02 9.3605E-03 2.4117E-021429000200075 7. 8. 8.5 3.4075E-02 9.6077E-03 2.6494E-021429000200076 7. 8. 9.5 2.5469E-02 8.3561E-03 2.3126E-021429000200077 ENDDATA 65 0 1429000200078 ENDSUBENT 77 0 1429000299999 SUBENT 14290003 20111006 13731429000300001 BIB 3 7 1429000300002 REACTION (94-PU-239(N,F),PR,NU/DE,,AV/REL) 1429000300003 Spectra are normalized to unity by integrating the 1429000300004 spectra in the 2.0-6.5 MeV emission energy range 1429000300005 ERR-ANALYS (ERR-S) Statistical uncertainty, considering 1429000300006 - foregound counting statistics (Poisson) 1429000300007 - background counting statistics (Gaussian) 1429000300008 STATUS (TABLE) Plotted in Fig.8 of Phys.Rev.C83(2011)034604 1429000300009 ENDBIB 7 0 1429000300010 NOCOMMON 0 0 1429000300011 DATA 6 63 1429000300012 EN-MIN EN-MAX E DATA -ERR-S +ERR-S 1429000300013 MEV MEV MEV ARB-UNITS ARB-UNITS ARB-UNITS 1429000300014 1. 2. 1.5 7.7570E-01 3.9848E-01 3.7451E-011429000300015 1. 2. 2.5 4.5988E-01 9.7521E-02 8.8112E-021429000300016 1. 2. 3.5 2.8451E-01 4.9955E-02 4.6290E-021429000300017 1. 2. 4.5 1.5683E-01 4.3520E-02 4.3625E-021429000300018 1. 2. 5.5 8.9706E-02 1.1697E-02 2.7095E-021429000300019 1. 2. 6.5 3.6339E-02 7.6946E-03 1.8397E-021429000300020 1. 2. 7.5 3.8058E-02 8.3967E-03 1.9877E-021429000300021 1. 2. 8.5 2.3065E-02 6.7523E-03 1.4861E-021429000300022 1. 2. 9.5 1.0977E-02 4.1974E-02 3.2265E-021429000300023 2. 3. 1.5 7.4984E-01 3.3942E-01 2.8682E-011429000300024 2. 3. 2.5 4.7250E-01 1.3241E-01 1.0184E-011429000300025 2. 3. 3.5 2.6341E-01 3.2492E-02 4.4873E-021429000300026 2. 3. 4.5 1.6453E-01 2.5582E-02 3.7220E-021429000300027 2. 3. 5.5 8.0302E-02 1.2350E-02 2.7986E-021429000300028 2. 3. 6.5 7.7074E-02 1.2189E-02 2.9228E-021429000300029 2. 3. 7.5 3.5303E-02 8.5237E-03 2.1591E-021429000300030 2. 3. 8.5 2.4068E-02 7.2662E-03 1.9814E-021429000300031 2. 3. 9.5 1.3579E-02 5.7268E-03 1.4410E-021429000300032 3. 4. 1.5 7.7866E-01 3.0643E-01 2.6904E-011429000300033 3. 4. 2.5 4.6975E-01 6.7530E-02 7.4040E-021429000300034 3. 4. 3.5 3.1730E-01 4.9335E-02 6.0727E-021429000300035 3. 4. 4.5 1.2075E-01 6.6902E-02 6.2013E-021429000300036 3. 4. 5.5 7.3572E-02 1.4108E-02 3.5848E-021429000300037 3. 4. 6.5 7.4519E-02 1.4401E-02 3.4364E-021429000300038 3. 4. 7.5 6.0470E-02 1.3401E-02 3.3827E-021429000300039 3. 4. 8.5 3.3127E-02 9.9013E-03 2.6597E-021429000300040 3. 4. 9.5 2.7786E-02 8.9714E-03 2.3577E-021429000300041 4. 5. 1.5 7.1451E-01 3.8469E-01 3.3856E-011429000300042 4. 5. 2.5 5.2280E-01 8.6111E-02 9.5636E-021429000300043 4. 5. 3.5 2.4253E-01 2.7239E-02 5.7299E-021429000300044 4. 5. 4.5 1.4929E-01 3.0992E-02 4.9596E-021429000300045 4. 5. 5.5 6.9890E-02 1.3804E-02 3.6864E-021429000300046 4. 5. 6.5 6.1956E-02 1.3685E-02 3.4441E-021429000300047 4. 5. 7.5 2.5208E-02 8.8228E-03 2.4441E-021429000300048 4. 5. 8.5 3.3742E-02 1.0683E-02 2.9612E-021429000300049 4. 5. 9.5 2.2165E-02 8.4650E-03 2.3480E-021429000300050 5. 6. 1.5 7.7687E-01 1.9477E-01 2.0100E-011429000300051 5. 6. 2.5 4.8908E-01 6.8152E-02 8.4556E-021429000300052 5. 6. 3.5 2.7739E-01 2.7716E-02 6.6719E-021429000300053 5. 6. 4.5 1.4633E-01 3.6798E-02 5.5340E-021429000300054 5. 6. 5.5 7.4950E-02 1.5034E-02 4.0328E-021429000300055 5. 6. 6.5 4.9020E-02 1.2967E-02 3.2640E-021429000300056 5. 6. 7.5 3.8650E-02 1.1468E-02 3.1796E-021429000300057 5. 6. 8.5 1.5784E-02 7.5024E-03 2.0785E-021429000300058 5. 6. 9.5 1.9506E-02 8.1840E-03 2.2684E-021429000300059 6. 7. 1.5 7.9991E-01 2.5899E-01 2.3366E-011429000300060 6. 7. 2.5 4.5110E-01 5.9917E-02 8.8513E-021429000300061 6. 7. 3.5 3.2262E-01 3.2167E-02 7.5665E-021429000300062 6. 7. 4.5 1.3034E-01 2.0502E-02 5.1415E-021429000300063 6. 7. 5.5 7.8678E-02 1.6465E-02 4.2922E-021429000300064 6. 7. 6.5 6.9048E-02 1.5932E-02 4.3079E-021429000300065 6. 7. 7.5 6.2342E-02 1.5060E-02 3.9505E-021429000300066 6. 7. 8.5 3.8633E-02 1.2519E-02 3.1682E-021429000300067 6. 7. 9.5 1.9061E-02 8.2029E-03 2.2693E-021429000300068 7. 8. 1.5 8.4894E-01 2.7090E-01 2.5559E-011429000300069 7. 8. 2.5 4.6296E-01 5.9930E-02 9.2218E-021429000300070 7. 8. 3.5 2.5936E-01 2.9185E-02 7.5015E-021429000300071 7. 8. 4.5 1.7984E-01 2.5403E-02 6.2184E-021429000300072 7. 8. 5.5 8.2861E-02 1.8021E-02 4.7731E-021429000300073 7. 8. 6.5 5.9923E-02 1.5692E-02 4.3467E-021429000300074 7. 8. 7.5 2.3143E-02 1.0107E-02 2.8000E-021429000300075 7. 8. 8.5 1.7731E-02 9.6817E-03 2.1304E-021429000300076 7. 8. 9.5 3.4108E-02 1.2876E-02 3.2926E-021429000300077 ENDDATA 65 0 1429000300078 ENDSUBENT 77 0 1429000399999 SUBENT 14290004 20111006 13731429000400001 BIB 3 10 1429000400002 REACTION ((94-PU-239(N,F),PR,NU/DE,,AV/REL)/ 1429000400003 (92-U-235(N,F),PR,NU/DE,,AV/REL)) 1429000400004 Ratio normalized to unity in the 2-3 MeV outgoing 1429000400005 energy range 1429000400006 ERR-ANALYS (ERR-S) Statistical uncertainty, considering 1429000400007 - foregound counting statistics (Poisson) 1429000400008 - background counting statistics (Gaussian) 1429000400009 STATUS (TABLE) Plotted in Fig.11 of Phys.Rev.C83(2011)034604 1429000400010 (DEP,14290002) U-235 prompt fission neutron spectra 1429000400011 (DEP,14290003) Pu-239 prompt fission neutron spectra 1429000400012 ENDBIB 10 0 1429000400013 NOCOMMON 0 0 1429000400014 DATA 6 63 1429000400015 EN-MIN EN-MAX E DATA -ERR-S +ERR-S 1429000400016 MEV MEV MEV ARB-UNITS ARB-UNITS ARB-UNITS 1429000400017 1. 2. 1.5 1.1274 0.7708 0.70031429000400018 1. 2. 2.5 1.0000 0.4278 0.37261429000400019 1. 2. 3.5 1.1678 0.2910 0.27361429000400020 1. 2. 4.5 1.3124 0.3812 0.42371429000400021 1. 2. 5.5 1.3310 0.2329 0.52621429000400022 1. 2. 6.5 1.2212 0.3409 0.81201429000400023 1. 2. 7.5 1.4231 0.4235 1.02721429000400024 1. 2. 8.5 1.2016 0.4566 1.03201429000400025 1. 2. 9.5 0.8737 3.3513 2.63691429000400026 2. 3. 1.5 0.9177 0.5798 0.50091429000400027 2. 3. 2.5 1.0000 0.5476 0.40061429000400028 2. 3. 3.5 0.9539 0.1860 0.21731429000400029 2. 3. 4.5 1.1194 0.2085 0.32401429000400030 2. 3. 5.5 1.1961 0.2462 0.55661429000400031 2. 3. 6.5 1.8068 0.4275 1.05561429000400032 2. 3. 7.5 1.0991 0.3501 0.86161429000400033 2. 3. 8.5 0.8103 0.3018 0.79781429000400034 2. 3. 9.5 0.8159 0.4269 1.09881429000400035 3. 4. 1.5 1.0120 0.5409 0.47571429000400036 3. 4. 2.5 1.0001 0.4284 0.34231429000400037 3. 4. 3.5 1.1606 0.2700 0.29781429000400038 3. 4. 4.5 0.9694 0.5491 0.55581429000400039 3. 4. 5.5 0.7721 0.1783 0.43991429000400040 3. 4. 6.5 1.5902 0.4226 1.02651429000400041 3. 4. 7.5 2.0874 0.6828 1.81201429000400042 3. 4. 8.5 1.3337 0.5408 1.37791429000400043 3. 4. 9.5 1.2675 0.6571 1.42531429000400044 4. 5. 1.5 0.8502 0.5443 0.47841429000400045 4. 5. 2.5 1.0001 0.2472 0.25151429000400046 4. 5. 3.5 0.8408 0.1427 0.24901429000400047 4. 5. 4.5 0.8242 0.1917 0.33391429000400048 4. 5. 5.5 1.1574 0.3111 0.82871429000400049 4. 5. 6.5 1.3742 0.4276 1.10541429000400050 4. 5. 7.5 0.5599 0.2361 0.64141429000400051 4. 5. 8.5 1.0870 0.4683 1.20241429000400052 4. 5. 9.5 1.3830 0.7743 2.14471429000400053 5. 6. 1.5 1.1476 0.4028 0.40071429000400054 5. 6. 2.5 1.0000 0.2117 0.23301429000400055 5. 6. 3.5 0.9856 0.1627 0.30271429000400056 5. 6. 4.5 1.0528 0.2934 0.49801429000400057 5. 6. 5.5 0.7581 0.2026 0.49421429000400058 5. 6. 6.5 0.8580 0.2816 0.73271429000400059 5. 6. 7.5 0.6291 0.2268 0.60131429000400060 5. 6. 8.5 0.7566 0.4382 1.19731429000400061 5. 6. 9.5 0.9133 0.5551 1.36171429000400062 6. 7. 1.5 1.0232 0.4616 0.40871429000400063 6. 7. 2.5 1.0000 0.3332 0.32671429000400064 6. 7. 3.5 1.2378 0.1869 0.37021429000400065 6. 7. 4.5 0.8940 0.1816 0.42921429000400066 6. 7. 5.5 1.2947 0.3668 0.92931429000400067 6. 7. 6.5 1.4121 0.4514 1.20211429000400068 6. 7. 7.5 2.4169 0.9104 2.46601429000400069 6. 7. 8.5 1.4097 0.6325 1.62041429000400070 6. 7. 9.5 1.1433 0.6634 1.83411429000400071 7. 8. 1.5 1.1463 0.4719 0.43831429000400072 7. 8. 2.5 0.9999 0.1950 0.25091429000400073 7. 8. 3.5 1.1001 0.2160 0.40421429000400074 7. 8. 4.5 1.3795 0.2649 0.64481429000400075 7. 8. 5.5 0.6989 0.1967 0.46961429000400076 7. 8. 6.5 1.5852 0.5655 1.52381429000400077 7. 8. 7.5 0.6742 0.3430 0.93321429000400078 7. 8. 8.5 0.5437 0.3341 0.77811429000400079 7. 8. 9.5 1.3992 0.6998 1.85441429000400080 ENDDATA 65 0 1429000400081 ENDSUBENT 80 0 1429000499999 SUBENT 14290005 20111006 13731429000500001 BIB 5 7 1429000500002 REACTION (92-U-235(N,F)0-NN-1,PR,KE,,AV) 1429000500003 ANALYSIS Measured spectra were fitted with TKE as fitting 1429000500004 parameter, and extrapolated by Los Alamos Model. 1429000500005 MISC-COL (MISC) Total kinetic energy used in model calculation 1429000500006 ERR-ANALYS (DATA-ERR) Due to uncertainty in TKE used in LANL model1429000500007 STATUS (TABLE) Plotted in Fig.12 of Phys.Rev.C83(2011)034604 1429000500008 (DEP,14290002) U-235 prompt fission neutron spectra 1429000500009 ENDBIB 7 0 1429000500010 NOCOMMON 0 0 1429000500011 DATA 8 7 1429000500012 EN-MIN EN-MAX DATA -DATA-ERR +DATA-ERR MISC 1429000500013 -MISC-ERR +MISC-ERR 1429000500014 MEV MEV MEV MEV MEV MEV 1429000500015 MEV MEV 1429000500016 1. 2. 1.98187 0.08776 0.07032 175.1 1429000500017 3.1 3.1 1429000500018 2. 3. 2.03241 0.10097 0.08838 173.0 1429000500019 4.2 4.1 1429000500020 3. 4. 2.07951 0.12524 0.10769 170.8 1429000500021 5.7 5.6 1429000500022 4. 5. 2.05074 0.16092 0.08412 175.0 1429000500023 5.5 5.4 1429000500024 5. 6. 2.18318 0.21071 0.09486 171.7 1429000500025 7.3 7.4 1429000500026 6. 7. 2.04660 0.15124 0.09984 178.4 1429000500027 5.2 5.2 1429000500028 7. 8. 2.13830 0.16320 0.15835 174.2 1429000500029 7.5 7.6 1429000500030 ENDDATA 18 0 1429000500031 ENDSUBENT 30 0 1429000599999 SUBENT 14290006 20111006 13731429000600001 BIB 5 7 1429000600002 REACTION (94-PU-239(N,F)0-NN-1,PR,KE,,AV) 1429000600003 ANALYSIS Measured spectra were fitted with TKE as fitting 1429000600004 parameter, and extrapolated by Los Alamos Model. 1429000600005 MISC-COL (MISC) Total kinetic energy used in model calculation 1429000600006 ERR-ANALYS (DATA-ERR) Due to uncertainty in TKE used in LANL model1429000600007 STATUS (TABLE) Plotted in Fig.13 of Phys.Rev.C83(2011)034604 1429000600008 (DEP,14290003) Pu-239 prompt fission neutron spectra 1429000600009 ENDBIB 7 0 1429000600010 NOCOMMON 0 0 1429000600011 DATA 8 7 1429000600012 EN-MIN EN-MAX DATA -DATA-ERR +DATA-ERR MISC 1429000600013 -MISC-ERR +MISC-ERR 1429000600014 MEV MEV MEV MEV MEV MEV 1429000600015 MEV MEV 1429000600016 1. 2. 2.17681 0.10708 0.17016 175.5 1429000600017 7.1 7.1 1429000600018 2. 3. 2.18727 0.19897 0.08273 180.6 1429000600019 6.6 6.6 1429000600020 3. 4. 2.10099 0.22664 0.13198 184.9 1429000600021 7.7 7.7 1429000600022 4. 5. 2.01938 0.22958 0.06812 190.9 1429000600023 5.5 5.6 1429000600024 5. 6. 2.07364 0.19338 0.13486 187.8 1429000600025 6.9 6.9 1429000600026 6. 7. 2.16173 0.25413 0.11292 186.8 1429000600027 8.1 8.1 1429000600028 7. 8. 2.17660 0.19429 0.18832 184.1 1429000600029 9.2 9.2 1429000600030 ENDDATA 18 0 1429000600031 ENDSUBENT 30 0 1429000699999 SUBENT 14290007 20190529 14521429000700001 BIB 6 8 1429000700002 REACTION (28-NI-0(N,INL)28-NI-0,,DE,,AV) 1429000700003 PART-DET (N,G) 1429000700004 METHOD (COINC) Neutron spectra gated on the 1429000700005 first 2+ to ground state transition 1429000700006 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1429000700007 STATUS (CURVE) Fig.6 from Kor.Phys.Soc.,59,1553,2011 was 1429000700008 digitized by GSYS2.4.7. 1429000700009 HISTORY (20190529C) OG. 1429000700010 ENDBIB 8 0 1429000700011 NOCOMMON 0 0 1429000700012 DATA 5 105 1429000700013 EN-MIN EN-MAX E DATA DATA-ERR 1429000700014 MEV MEV MEV MB/MEV MB/MEV 1429000700015 6. 7. 1.1416 4.3205 5.8995 1429000700016 6. 7. 1.2313 19.5537 4.9139 1429000700017 6. 7. 1.3503 16.1054 5.4061 1429000700018 6. 7. 1.4304 44.6117 6.8826 1429000700019 6. 7. 1.5492 33.2982 4.4229 1429000700020 6. 7. 1.6689 54.4285 8.3579 1429000700021 6. 7. 1.7578 37.7096 6.3904 1429000700022 6. 7. 1.8578 65.7231 7.3730 1429000700023 6. 7. 1.9468 52.9367 6.8820 1429000700024 6. 7. 2.1455 61.2812 8.8495 1429000700025 6. 7. 2.3834 49.9604 6.3898 1429000700026 6. 7. 2.4533 64.7033 5.8976 1429000700027 6. 7. 2.5719 45.5247 5.4049 1429000700028 6. 7. 2.6519 70.0984 7.3730 1429000700029 6. 7. 2.7610 64.6844 7.3724 1429000700030 6. 7. 2.8507 81.3924 8.8471 1429000700031 6. 7. 2.9699 83.3514 8.8477 1429000700032 6. 7. 3.0794 99.5665 9.3374 1429000700033 6. 7. 3.1590 107.4268 11.3068 1429000700034 6. 7. 3.2886 127.5733 11.3037 1429000700035 6. 7. 3.3584 142.3162 13.7652 1429000700036 6. 7. 3.4876 146.2409 10.8134 1429000700037 6. 7. 3.5478 172.7821 12.7803 1429000700038 6. 7. 3.6571 177.6911 14.2550 1429000700039 6. 7. 3.7962 183.5815 12.2881 1429000700040 6. 7. 3.8765 217.9866 17.2056 1429000700041 6. 7. 3.9953 207.1647 13.2724 1429000700042 6. 7. 4.0758 251.4014 14.7459 1429000700043 6. 7. 4.1845 230.7486 11.7965 1429000700044 6. 7. 4.2650 274.0021 13.7622 1429000700045 6. 7. 4.3647 294.6420 15.2393 1429000700046 6. 7. 4.4839 299.0588 17.6966 1429000700047 6. 7. 4.5646 347.7196 18.6797 1429000700048 6. 7. 4.7025 308.3853 17.2056 1429000700049 6. 7. 4.7715 287.2434 15.7303 1429000700050 6. 7. 4.8895 242.0115 15.7297 1429000700051 6. 7. 5.0077 207.1025 13.2712 1429000700052 6. 7. 5.0762 168.2641 12.2905 1429000700053 6. 7. 5.2253 177.5948 12.2887 1429000700054 6. 7. 5.2934 123.0260 8.8477 1429000700055 6. 7. 5.4026 121.5446 9.8296 1429000700056 6. 7. 5.4908 79.2639 8.3555 1429000700057 6. 7. 5.5995 60.0859 6.8808 1429000700058 6. 7. 5.7181 38.9409 5.4049 1429000700059 6. 7. 5.8169 19.2719 4.9145 1429000700060 6. 7. 5.9258 6.9759 4.9151 1429000700061 6. 7. 6.0050 0.0890 4.4248 1429000700062 7. 8. 1.0420 12.8397 4.2799 1429000700063 7. 8. 1.1204 23.3016 4.7554 1429000700064 7. 8. 1.3221 26.1549 6.6576 1429000700065 7. 8. 1.4566 31.3858 4.7554 1429000700066 7. 8. 1.5910 29.0081 3.8043 1429000700067 7. 8. 1.6695 16.1685 5.2310 1429000700068 7. 8. 1.8263 20.9239 3.3288 1429000700069 7. 8. 1.9496 26.1549 2.8533 1429000700070 7. 8. 2.0728 31.3858 3.3288 1429000700071 7. 8. 2.1176 23.7772 6.1821 1429000700072 7. 8. 2.1849 22.8261 6.6576 1429000700073 7. 8. 2.3193 19.9728 3.8043 1429000700074 7. 8. 2.3978 25.2038 6.1821 1429000700075 7. 8. 2.4650 31.3858 9.0353 1429000700076 7. 8. 2.5434 38.9945 8.0842 1429000700077 7. 8. 2.6331 40.8967 7.1331 1429000700078 7. 8. 2.7563 44.7010 5.7065 1429000700079 7. 8. 2.8796 38.5190 5.7065 1429000700080 7. 8. 2.9468 45.6521 4.2799 1429000700081 7. 8. 3.0476 57.5407 6.6576 1429000700082 7. 8. 3.1597 60.8695 5.7065 1429000700083 7. 8. 3.2493 66.1005 5.2310 1429000700084 7. 8. 3.3277 64.1983 7.6087 1429000700085 7. 8. 3.4398 75.6113 9.0353 1429000700086 7. 8. 3.5966 79.4157 10.4619 1429000700087 7. 8. 3.6751 91.7798 9.5109 1429000700088 7. 8. 3.7647 99.3885 10.4619 1429000700089 7. 8. 3.9104 106.9972 9.0353 1429000700090 7. 8. 3.9888 119.3613 10.9375 1429000700091 7. 8. 4.0560 129.8233 11.4130 1429000700092 7. 8. 4.1793 134.1031 10.9375 1429000700093 7. 8. 4.2801 141.2363 11.8886 1429000700094 7. 8. 4.4034 153.6004 12.8397 1429000700095 7. 8. 4.4706 182.6085 15.2174 1429000700096 7. 8. 4.5826 211.1411 12.8397 1429000700097 7. 8. 4.6723 219.7009 13.7907 1429000700098 7. 8. 4.7395 208.7634 14.7418 1429000700099 7. 8. 4.8739 217.3232 15.6929 1429000700100 7. 8. 5.0084 220.6520 12.3641 1429000700101 7. 8. 5.0980 244.9047 14.7418 1429000700102 7. 8. 5.1877 260.5976 15.2174 1429000700103 7. 8. 5.3109 255.3666 13.3152 1429000700104 7. 8. 5.3894 275.8150 17.5951 1429000700105 7. 8. 5.4902 282.9481 17.1195 1429000700106 7. 8. 5.6134 277.7171 18.0706 1429000700107 7. 8. 5.7031 249.6601 14.2663 1429000700108 7. 8. 5.8039 205.9101 13.7907 1429000700109 7. 8. 5.8824 184.5107 13.3152 1429000700110 7. 8. 6.0280 171.6710 11.8886 1429000700111 7. 8. 6.1289 145.9917 9.9864 1429000700112 7. 8. 6.2297 125.0678 10.4619 1429000700113 7. 8. 6.3305 103.6684 9.0353 1429000700114 7. 8. 6.4090 87.0244 7.1331 1429000700115 7. 8. 6.4986 53.2608 6.6576 1429000700116 7. 8. 6.5882 16.1685 4.2799 1429000700117 7. 8. 6.7115 5.2310 3.8043 1429000700118 7. 8. 6.7899 0.0010 2.8533 1429000700119 7. 8. 6.8683 3.3288 3.3288 1429000700120 ENDDATA 107 0 1429000700121 ENDSUBENT 120 0 1429000799999 ENDENTRY 7 0 1429099999999