ENTRY 30426 20110816 31513042600000001 SUBENT 30426001 20110816 31513042600100001 BIB 14 35 3042600100002 TITLE The prompt neutron spectrum from thermal neutron- 3042600100003 induced fission of U-235 for the energy range 30 keV 3042600100004 to 1 MeV 3042600100005 AUTHOR (A.Lajtai, J.Kecskemeti, D.Kluge, G.Petravich, 3042600100006 P.P.D'yachenko, V.M.Piksajkin) 3042600100007 INSTITUTE (3HUNKFI,4RUSFEI) 3042600100008 REFERENCE (C,77KIEV,3,26,197704) Contribution paper in Russian 3042600100009 (R,INDC(HUN)-14,197802) English translation by IAEA 3042600100010 (C,75KIEV,5,146,197504) Preliminary result 3042600100011 FACILITY (REAC,3HUNKFI) VVR-S reactor 3042600100012 INC-SOURCE (REAC) 3042600100013 INC-SPECT Thermal neutrons 3042600100014 METHOD (TOF) Flight path = 30 cm, channel time = 0.47 ns/ch 3042600100015 (COINC) Fission neutron and fragment detectors in 3042600100016 coincident mode (delayed coincidence) 3042600100017 Cf-252 was used as reference source. 3042600100018 DETECTOR (SCIN) 3042600100019 -Pure argon gas scintillation chamber as fission 3042600100020 fragment detector; 3042600100021 -NE-912 lithium glass scintillator with 56-AVP photo- 3042600100022 multiplier as neutron detector; 3042600100023 -NE-913 Li-glass scintillator for measurement of 3042600100024 delayed gamma-ray background. 3042600100025 PART-DET (N,FF) 3042600100026 MONITOR ((MONIT1)98-CF-252(0,F),PR,NU) = 3.74 3042600100027 ((MONIT2)92-U-235(N,F),PR,NU) = 2.40 3042600100028 1(98-CF-252(0,F),PR,DE,N) 3042600100029 Prompt neutron spectrum of Cf-252 3042600100030 MONIT-REF 1(,P.P.D'yachenko+,J,AE,42,25,1977) 3042600100031 CORRECTION Scattered neutrons are corrected. 3042600100032 HISTORY (19780118C) KO. 3042600100033 (20090310A) SD:Updated to new date formats,lower case. 3042600100034 OS. Added FCT to Reaction and comment, Units changed, 3042600100035 Monitor coding corrected 3042600100036 (20110518A) On. METHOD: COINC added 3042600100037 ENDBIB 35 0 3042600100038 COMMON 2 3 3042600100039 MONIT1 MONIT2 3042600100040 PRT/FIS PRT/FIS 3042600100041 3.74 2.40 3042600100042 ENDCOMMON 3 0 3042600100043 ENDSUBENT 42 0 3042600199999 SUBENT 30426002 20110816 31513042600200001 BIB 6 12 3042600200002 REACTION (92-U-235(N,F),PR,NU/DE,,MXW/FCT) 3042600200003 Units in Fig. 4 are "neutrons/MeV*steradian" 3042600200004 though no angle and no angular dependence given. 3042600200005 EN-SEC (E,N) 3042600200006 ANALYSIS Measured counts were divided by neutron multiplicity 3042600200007 and solid angle. 3042600200008 STATUS (TABLE) Numerical values from Kecskemeti, 78/01/05, 3042600200009 corresponding to Fig.4 of contribution paper to 3042600200010 4th All Union Conf. on Neutron Physics, Kiev, 1977 3042600200011 ERR-ANALYS (ERR-S) Statistical uncertainty 3042600200012 HISTORY (20110518A) On. PR,DE,N,MXW/FCT -> PR,NU/DE,,MXW/FCT 3042600200013 (20110816A) On. ANALYSIS added. 3042600200014 ENDBIB 12 0 3042600200015 COMMON 1 3 3042600200016 EN-DUMMY 3042600200017 EV 3042600200018 0.0253 3042600200019 ENDCOMMON 3 0 3042600200020 DATA 3 40 3042600200021 E DATA ERR-S 3042600200022 MEV PT/FIS/MEV PT/FIS/MEV 3042600200023 3.0000E-02 1.2000E-02 5.0000E-03 3042600200024 6.0000E-02 2.0000E-02 4.0000E-03 3042600200025 9.0000E-02 2.2000E-02 4.0000E-03 3042600200026 1.2000E-01 1.8000E-02 4.0000E-03 3042600200027 1.5000E-01 2.7000E-02 4.0000E-03 3042600200028 1.8000E-01 2.4000E-02 4.0000E-03 3042600200029 2.1000E-01 2.8000E-02 4.0000E-03 3042600200030 2.4000E-01 3.1000E-02 4.0000E-03 3042600200031 2.7000E-01 3.3000E-02 4.0000E-03 3042600200032 3.0000E-01 3.1000E-02 4.0000E-03 3042600200033 3.3000E-01 3.2000E-02 4.0000E-03 3042600200034 3.6000E-01 3.2000E-02 4.0000E-03 3042600200035 3.9000E-01 3.5000E-02 4.0000E-03 3042600200036 4.2000E-01 3.7000E-02 3.0000E-03 3042600200037 4.5000E-01 3.7000E-02 3.0000E-03 3042600200038 4.8000E-01 3.6000E-02 3.0000E-03 3042600200039 5.1000E-01 3.7000E-02 3.0000E-03 3042600200040 5.4000E-01 3.8000E-02 3.0000E-03 3042600200041 5.7000E-01 3.6000E-02 3.0000E-03 3042600200042 6.0000E-01 3.6000E-02 3.0000E-03 3042600200043 6.3000E-01 3.6000E-02 3.0000E-03 3042600200044 6.6000E-01 3.6000E-02 3.0000E-03 3042600200045 6.9000E-01 3.5000E-02 3.0000E-03 3042600200046 7.2000E-01 3.6000E-02 3.0000E-03 3042600200047 7.5000E-01 3.6000E-02 3.0000E-03 3042600200048 7.8000E-01 3.6000E-02 3.0000E-03 3042600200049 8.1000E-01 3.7000E-02 3.0000E-03 3042600200050 8.4000E-01 3.5000E-02 3.0000E-03 3042600200051 8.7000E-01 3.4000E-02 3.0000E-03 3042600200052 9.0000E-01 3.6000E-02 3.0000E-03 3042600200053 9.3000E-01 3.3000E-02 3.0000E-03 3042600200054 9.6000E-01 3.3000E-02 3.0000E-03 3042600200055 9.9000E-01 3.2000E-02 3.0000E-03 3042600200056 1.0200E+00 3.2000E-02 2.0000E-03 3042600200057 1.0500E+00 3.2000E-02 2.0000E-03 3042600200058 1.0800E+00 3.0000E-02 2.0000E-03 3042600200059 1.1100E+00 2.8000E-02 2.0000E-03 3042600200060 1.1400E+00 3.0000E-02 2.0000E-03 3042600200061 1.1700E+00 2.9000E-02 2.0000E-03 3042600200062 1.2000E+00 2.8000E-02 2.0000E-03 3042600200063 ENDDATA 42 0 3042600200064 ENDSUBENT 63 0 3042600299999 ENDENTRY 2 0 3042699999999