ENTRY 20392 20101107 22252039200000001 SUBENT 20392001 20101107 22252039200100001 BIB 13 36 2039200100002 INSTITUTE (2ZZZGEL) 2039200100003 REFERENCE (J,ZP,232,286,197011) 2039200100004 (C,70HELSINKI,2,863,197006) analytical result +Benzi+.2039200100005 (C,71VIENNA,,41,197108) Same curves for n-spectra given2039200100006 (J,NSD/BS,1,33,197704) Kin.energy is given. + 2039200100007 similar review to 71Vienna 2039200100008 REL-REF (O,20136001,H.-H.Knitter+,J,ZP,228,286,1969) 2039200100009 see EXFOR entry 20136 for angular 2039200100010 distributions in the lower energies. 2039200100011 AUTHOR (M.Coppola, H.-H.Knitter) 2039200100012 TITLE -Interactions of neutrons with Pu-239 in the energy 2039200100013 range between 1.5 and 5.5 MeV.- 2039200100014 FACILITY (VDG,2ZZZGEL) 3 MV Van de Graaff accelerator,1 ns pulse2039200100015 width, 1 MHz repetition rate. 2039200100016 INC-SOURCE (P-T ) Proton-tritium for 1.5, 1.9, 2.3 MeV neutron2039200100017 Ti-T target, energy spread of 91,81,74keV respectively2039200100018 (D-D ) deuteron-deuteron for 4.0, 4.5, 5.0 and 5.5 2039200100019 MeV neutron, gas target, E-spread of 198, 138, 104 and2039200100020 81 keV respectively. 2039200100021 SAMPLE .Solid cylinder of 1.2 cm dia.,2.5 cm height, 54.803gr,2039200100022 canned in a zircalloy container. 2039200100023 METHOD (TOF ) Time of flight. 2039200100024 DETECTOR (SCIN ) 3 Cylindrical Ne 102A plastic scintillators,2039200100025 5.0 cm in dia. 2.5 thick viewed by AVP56/03 phototubes2039200100026 .4Th TOF spectrometer of same type as n-flux monitor. 2039200100027 CORRECTION .Corrected for sample size, beam attenuation and 2039200100028 multiple scattering using program 'MAGGIE'. 2039200100029 STATUS (TABLE) Data from Z.Phys.232,286. 2039200100030 HISTORY (19730208C) 2039200100031 (19741011E) 2039200100032 (19810119A) Reference added. 2039200100033 (19810213E) 2039200100034 (20101107A) SD:Updated to new date formats,lower case. 2039200100035 corrected according to last EXFOR rules and Dict. 2039200100036 Data set in Subent 004 was restored. 2039200100037 ref. on ZP,228,286,1969 moved to REL-REF 2039200100038 ENDBIB 36 0 2039200100039 NOCOMMON 0 0 2039200100040 ENDSUBENT 39 0 2039200199999 SUBENT 20392002 20101107 22252039200200001 BIB 6 16 2039200200002 REACTION (94-PU-239(N,SCT)94-PU-239,PAR,DA) scattering 2039200200003 angular distribution. 2039200200004 ANALYSIS .Contribution of fission neutrons and gamma-ray 2039200200005 background was subtracted from the T.O.F. Spectra of 2039200200006 emitted neutrons in the region of the elastic peak. 2039200200007 MONITOR (1-H-1(N,EL)1-H-1,,DA) Elastic scattering from a 2039200200008 hollow polyethylene cylinder. No normalisation value 2039200200009 given. 2039200200010 STATUS (TABLE) Table 1 in ZP,232,286. 2039200200011 HISTORY (19810119A) reaction re-coded. 2039200200012 (19810213E) 2039200200013 (20101107A) SD: values of EN-RSL were corrected 2039200200014 according to the text on p.287 of ZP,232,286 2039200200015 REACTION code was corrected: SF3: EL -> SCT; 2039200200016 SF5 -> PAR; col.E-EXC-MAX in DATA was added. 2039200200017 ERR-ANALYS (ERR-S) Statistical error only. 2039200200018 ENDBIB 16 0 2039200200019 NOCOMMON 0 0 2039200200020 DATA 6 74 2039200200021 EN EN-RSL E-EXC-MAX ANG DATA ERR-S 2039200200022 MEV MEV MEV ADEG MB/SR MB/SR 2039200200023 1.5 0.091 0.300 148.0 30.3 2.52039200200024 1.5 0.091 0.300 130.0 76.1 4.22039200200025 1.5 0.091 0.300 115.0 164.9 8.52039200200026 1.5 0.091 0.300 105.0 208.6 10.22039200200027 1.5 0.091 0.300 90.0 230.2 11.72039200200028 1.5 0.091 0.300 75.0 159.6 8.12039200200029 1.5 0.091 0.300 60.0 110.3 6.42039200200030 1.5 0.091 0.300 45.0 357.2 16.82039200200031 1.5 0.091 0.300 35.0 619.14 28.52039200200032 1.5 0.091 0.300 25.0 1204.57 53.72039200200033 1.9 0.081 0.300 148.0 40.4 2.82039200200034 1.9 0.081 0.300 130.0 41.8 2.52039200200035 1.9 0.081 0.300 115.0 98.4 5.62039200200036 1.9 0.081 0.300 105.0 144.8 7.82039200200037 1.9 0.081 0.300 90.0 192.6 9.52039200200038 1.9 0.081 0.300 75.0 147.2 8.22039200200039 1.9 0.081 0.300 60.0 81.6 5.12039200200040 1.9 0.081 0.300 45.0 187.6 9.62039200200041 1.9 0.081 0.300 35.0 687.1 30.92039200200042 1.9 0.081 0.300 25.0 1557.3 69.32039200200043 2.3 0.074 0.300 148.0 44.4 2.92039200200044 2.3 0.074 0.300 130.0 58.0 3.62039200200045 2.3 0.074 0.300 115.0 52.7 4.2039200200046 2.3 0.074 0.300 105.0 100.1 5.92039200200047 2.3 0.074 0.300 90.0 169.0 9.12039200200048 2.3 0.074 0.300 75.0 160.2 8.62039200200049 2.3 0.074 0.300 60.0 49.3 2.42039200200050 2.3 0.074 0.300 45.0 251.9 12.22039200200051 2.3 0.074 0.300 35.0 958.1 43.62039200200052 2.3 0.074 0.300 25.0 2084.3 93.62039200200053 4.0 0.198 1.0 148.0 56.4 5.22039200200054 4.0 0.198 1.0 133.0 65.0 4.32039200200055 4.0 0.198 1.0 115.0 29.4 3.62039200200056 4.0 0.198 1.0 100.0 63.0 4.12039200200057 4.0 0.198 1.0 90.0 90.5 7.92039200200058 4.0 0.198 1.0 75.0 196.5 12.82039200200059 4.0 0.198 1.0 60.0 82.7 7.22039200200060 4.0 0.198 1.0 45.0 108.3 5.62039200200061 4.0 0.198 1.0 35.0 734.9 35.12039200200062 4.0 0.198 1.0 30.0 1503.5 68.62039200200063 4.0 0.198 1.0 25.0 2225.4 102.12039200200064 4.5 0.138 1.0 148.0 39.6 3.92039200200065 4.5 0.138 1.0 133.0 58.8 4.52039200200066 4.5 0.138 1.0 115.0 23.3 2.82039200200067 4.5 0.138 1.0 100.0 54.7 5.82039200200068 4.5 0.138 1.0 90.0 68.6 5.92039200200069 4.5 0.138 1.0 75.0 110.2 8.72039200200070 4.5 0.138 1.0 60.0 73.1 6.52039200200071 4.5 0.138 1.0 45.0 106.3 7.82039200200072 4.5 0.138 1.0 35.0 526.3 26.52039200200073 4.5 0.138 1.0 30.0 1058.6 48.82039200200074 4.5 0.138 1.0 25.0 2088.2 96.72039200200075 5.0 0.104 1.0 148.0 34.6 3.42039200200076 5.0 0.104 1.0 133.0 43.8 4.22039200200077 5.0 0.104 1.0 115.0 13.1 2.02039200200078 5.0 0.104 1.0 100.0 50.3 5.42039200200079 5.0 0.104 1.0 90.0 64.5 6.12039200200080 5.0 0.104 1.0 75.0 123.8 9.52039200200081 5.0 0.104 1.0 60.0 75.3 6.42039200200082 5.0 0.104 1.0 45.0 72.3 6.42039200200083 5.0 0.104 1.0 35.0 541.6 27.42039200200084 5.0 0.104 1.0 30.0 955. 45.12039200200085 5.0 0.104 1.0 25.0 1976.8 92.12039200200086 5.5 0.081 1.0 148.0 29.0 2.62039200200087 5.5 0.081 1.0 133.0 43.5 3.52039200200088 5.5 0.081 1.0 115.0 20.5 2.12039200200089 5.5 0.081 1.0 100.0 56.3 4.82039200200090 5.5 0.081 1.0 90.0 68.2 5.62039200200091 5.5 0.081 1.0 75.0 100.0 7.02039200200092 5.5 0.081 1.0 60.0 59.4 4.42039200200093 5.5 0.081 1.0 45.0 102.7 6.62039200200094 5.5 0.081 1.0 35.0 216.7 11.42039200200095 5.5 0.081 1.0 30.0 965.3 45.22039200200096 5.5 0.081 1.0 25.0 1882.3 87.52039200200097 ENDDATA 76 0 2039200200098 ENDSUBENT 97 0 2039200299999 SUBENT 20392003 20101107 22252039200300001 BIB 5 16 2039200300002 REACTION (94-PU-239(N,F)0-NN-1,PR,KE) Average kinetic energy of 2039200300003 fission neutrons. 2039200300004 ANALYSIS .Up to 2.3 MeV, parameters of fission spectrum deduced 2039200300005 directly from T.O.F. Spectra of emitted neutrons. 2039200300006 Fission spectrum was represented as a Maxwellian. 2039200300007 .Above 2.3 MeV, after subtracting gamma-ray back ground2039200300008 the shape of fission plus inelastic neutron spectrum 2039200300009 were fitted, n(E)=C'*(square root(E))*(exp(-E/T')) + 2039200300010 C*(E)*(exp(-E/T)). T' corresponds to fission neutron 2039200300011 energy, T is the nucl.temp. from inelastic scattering.2039200300012 STATUS (TABLE) Table in ZP,232,286. 2039200300013 HISTORY (19810119A) reaction re-coded. 2039200300014 (19810213E) 2039200300015 (20101107A) SD: values of EN-RSL were corrected 2039200300016 according to the text on p.287 of ZP,232,286 2039200300017 ERR-ANALYS (ERR-S) Statistical error only. 2039200300018 ENDBIB 16 0 2039200300019 NOCOMMON 0 0 2039200300020 DATA 4 7 2039200300021 EN EN-RSL DATA ERR-S 2039200300022 MEV MEV MEV MEV 2039200300023 1.5000E+00 0.091 2.12 7.0000E-02 2039200300024 1.9000E+00 0.081 2.18 6.0000E-02 2039200300025 2.3000E+00 0.074 2.28 6.0000E-02 2039200300026 4.0000E+00 0.198 2.27 1.0000E-01 2039200300027 4.5000E+00 0.138 2.53 9.0000E-02 2039200300028 5.0000E+00 0.104 2.42 1.0000E-01 2039200300029 5.5000E+00 0.081 2.42 8.0000E-02 2039200300030 ENDDATA 9 0 2039200300031 ENDSUBENT 30 0 2039200399999 SUBENT 20392004 20101107 22252039200400001 BIB 6 16 2039200400002 REACTION (94-PU-239(0,0),,TEM) Nuclear temperature. 2039200400003 ANALYSIS .Up to 2.3 MeV, inelastic neutron spectra were fitted 2039200400004 with, N(E)=C*(E)*(exp(-E/T)). 2039200400005 .above 2.3 MeV, after subtracting gamma-ray back ground2039200400006 the shape of fission plus inelastic neutron spectrum 2039200400007 were fitted, n(E)=C'*(square root(E))*(exp(-E/T')) + 2039200400008 C*(E)*(exp(-E/T)). T' corresponds to fission neutron 2039200400009 energy, T is the nucl.temp. from inelastic scattering.2039200400010 MISC-COL (MISC) Incident neutron energy 2039200400011 STATUS (TABLE) Table in ZP,232,286. 2039200400012 HISTORY (19730208C) 2039200400013 (19741011E) 2039200400014 (19810119A) reaction re-coded. 2039200400015 (19810213E) 2039200400016 (20101107A) SD: Data set was restored. 2039200400017 ERR-ANALYS (ERR-S) Statistical error only. 2039200400018 ENDBIB 16 0 2039200400019 NOCOMMON 0 0 2039200400020 DATA 4 6 2039200400021 DATA ERR-S MISC MISC-ERR 2039200400022 MEV MEV MEV MEV 2039200400023 0.26 6.E-02 1.9 4.05E-02 2039200400024 0.22 2.E-02 2.3 3.7E-02 2039200400025 0.48 5.E-02 4. 9.9E-02 2039200400026 0.45 4.E-02 4.5 6.9E-02 2039200400027 0.39 5.E-02 5. 5.2E-02 2039200400028 0.48 5.E-02 5.5 4.05E-02 2039200400029 ENDDATA 8 0 2039200400030 ENDSUBENT 29 0 2039200499999 ENDENTRY 4 0 2039299999999