ENTRY 20158 19831109 00002015800000001 SUBENT 20158001 19831109 00002015800100001 BIB 13 46 2015800100002 INSTITUTE (2GERKFK) 2015800100003 REFERENCE (J,NSE,48,324,7207) FULL PAPER. 2015800100004 (R,KFK-1563,7203) DATA ARE SAMA AS THOSE IN 2015800100005 NUCL.SCI.ENG.,48(1972)324. 2015800100006 (C,71KNOX,,273,7103) +PRIV.COMM. DATA OUT OF DATE. 2015800100007 AUTHOR (R.-E.BANDL, H.MIESSNER, F.H.FROEHNER) 2015800100008 TITLE -A MEASUREMENT OF THE CAPTURE-TO-FISSION RATIO ALPHA 2015800100009 FOR U-235 AND PU-239 WITH A NEW TECHNIQUE.- 2015800100010 FACILITY (VDG ) 3 MV PULSED VAN DE GRAAFF ACCELERATOR, 2015800100011 PULSE LENGTH AFTER BUNCHING = 1 NS. 2015800100012 INC-SOURCE (P-LI7) LI7(P,N)BE7 REACTION. 2015800100013 INC-SPECT .A BROAD NEUTRON SPECTRUM WITH ENERGIES FROM 5 TO 70 2015800100014 KEV. THE NEUTRONS PRODUCED IN THIS ENERGY RANGE ARE 2015800100015 COLLIMATED KINEMATICALLY WITHIN ABOUT +- 30 DEG ,SO 2015800100016 NEITHER BEAM COLLIMATION NOR DETECTOR SHIELDING WAS 2015800100017 NECESSARY. 2015800100018 SAMPLE .ALL SAMPLES USED (PU, U AND PB) ARE 4 CM 2015800100019 DIAMETER METAL DISCS, 0.035 TO 0.05 ATOMS/BARN THICK, 2015800100020 AND PACKAGED IDENTICALLY IN 0.2 MM THICK COPPER. 2015800100021 METHOD (TOF ) TIME OF FLIGHT FOR DETERMINATION OF INCIDENT2015800100022 NEUTRON ENERGY, 2015800100023 .THE ESSENCE OF THIS EXPERIMENT IS APPLICATION OF 2015800100024 A NEW TECHNIQUE TO DETERMINE THE ALPHA-VALUES, 2015800100025 BASED SOLELY ON NEUTRON DETECTION. IT CONSISTS OF 2015800100026 SCATTERING, TRANSMISSION AND PROMPT FISSION NEUTRON 2015800100027 MEASUREMENTS. 2015800100028 DETECTOR (SCIN ) LI-6 GLASS SCINTILLATOR (NE905) OF 1.2 CM 2015800100029 THICKNESS AND 11 CM DIA. COUPLED TO AN XP1040 PHOTO- 2015800100030 MULTIPLIER FOR THE SCATTERED NEUTRONS, THE EFFICIENCY 2015800100031 OF THIS DETECTOR FOR FISSION NEUTRONS IS SMALL, 2015800100032 .PROTON RECOIL DETECTOR (LIQUID SCINTILLATOR 2015800100033 NE 213 WITH 3 CM THICKNESS AND 11 CM DIA. AND XP 1040 2015800100034 PHOTOMULTIPLIER) FOR THE PROMPT FISSION NEUTRONS. 2015800100035 (GLASD) LI6-GLASS DETECTOR FOR TRANSMISSION 2015800100036 MEASUREMENT, 2015800100037 .LI-6 DEPLETED GLASS SCINTILLATOR (NE 906) SERVED FOR 2015800100038 GAMMA RAY BACKGROUND. 2015800100039 STATUS .PRIVATE COMMUNICATION FROM BANDL, 09/12/71. 2015800100040 HISTORY (711217C) 2015800100041 (731005E) 2015800100042 CORRECTION .CORRECTIONS FOR INELASTIC SCATTERING IN THE FISSILE 2015800100043 SAMPLE, THE ENERGY-DEPENDENT ANGULAR DISTRIBUTION OF 2015800100044 SCATTERED NEUTRONS AND OTHERS ARE CONSIDERED. 2015800100045 .THE AVERAGE NUMBER OF NEUTRONS EMITTED PER FISSION IS 2015800100046 ASSUMED TO BE CONSTANT IN THE ENERGY RANGE OF PRESENT 2015800100047 EXPERIMENT. 2015800100048 ENDBIB 46 0 2015800100049 NOCOMMON 0 0 2015800100050 ENDSUBENT 49 0 2015800199999 SUBENT 20158002 19831109 00002015800200001 BIB 5 14 2015800200002 REACTION (92-U-235(N,ABS),,ALF) 2015800200003 MONITOR (92-U-235(N,ABS),,ALF) 2015800200004 RECOMMENDED VALUES OF ALTER AND DUNFORD, 2015800200005 AI-AEC-MEMO-12916(1970), IN THE ENERGY RANGE 2015800200006 40 TO 50 KEV. 2015800200007 PART-DET (N ) NEUTRONS 2015800200008 HISTORY (711217C) 2015800200009 (731005E) 2015800200010 ERR-ANALYS .TOTAL ERROR (SQUARE ROOT OF SUM OF SQUARE(SYSTEMATIC) 2015800200011 AND SQUARE(STATISTICAL)) ARE, 2015800200012 15, 14 AND 13 PER-CENT. 2015800200013 AT 10-20, 20-40 AND 40-50 KEV RESPECTIVELY. 2015800200014 .THE OVERALL TIME RESOLUTION WAS 20 NS/M.AND THE ENERGY2015800200015 RESOLUTION WAS 10 PERCENT AT 30 KEV NEUTRON ENERGY. 2015800200016 ENDBIB 14 0 2015800200017 NOCOMMON 0 0 2015800200018 DATA 4 21 2015800200019 EN-MAX EN-MIN DATA DATA-ERR 2015800200020 MEV MEV NO-DIM NO-DIM 2015800200021 9.0000E-03 8.0000E-03 4.0000E-01 7.0000E-02 2015800200022 1.0000E-02 9.0000E-03 3.4000E-01 6.0000E-02 2015800200023 1.1000E-02 1.0000E-02 3.7000E-01 6.0000E-02 2015800200024 1.2000E-02 1.1000E-02 4.1000E-01 6.0000E-02 2015800200025 1.3000E-02 1.2000E-02 3.5000E-01 5.0000E-02 2015800200026 1.4000E-02 1.3000E-02 3.4000E-01 5.0000E-02 2015800200027 1.5000E-02 1.4000E-02 4.4000E-01 5.0000E-02 2015800200028 1.6000E-02 1.5000E-02 4.5000E-01 5.0000E-02 2015800200029 1.7000E-02 1.6000E-02 4.2000E-01 5.0000E-02 2015800200030 1.8000E-02 1.7000E-02 3.7000E-01 5.0000E-02 2015800200031 1.9000E-02 1.8000E-02 3.4000E-01 5.0000E-02 2015800200032 2.0000E-02 1.9000E-02 3.6000E-01 5.0000E-02 2015800200033 2.2500E-02 2.0000E-02 3.5000E-01 5.0000E-02 2015800200034 2.5000E-02 2.2500E-02 2.8000E-01 5.0000E-02 2015800200035 2.7500E-02 2.5000E-02 2.7000E-01 4.0000E-02 2015800200036 3.0000E-02 2.7500E-02 2.8000E-01 4.0000E-02 2015800200037 3.5000E-02 3.0000E-02 3.2000E-01 4.0000E-02 2015800200038 4.0000E-02 3.5000E-02 3.5000E-01 4.0000E-02 2015800200039 4.5000E-02 4.0000E-02 3.3000E-01 4.0000E-02 2015800200040 5.0000E-02 4.5000E-02 3.7000E-01 5.0000E-02 2015800200041 6.0000E-02 5.0000E-02 3.6000E-01 5.0000E-02 2015800200042 ENDDATA 23 0 2015800200043 ENDSUBENT 42 0 2015800299999 SUBENT 20158003 19831109 00002015800300001 BIB 5 16 2015800300002 REACTION (94-PU-239(N,ABS),,ALF) 2015800300003 MONITOR (94-PU-239(N,ABS),,ALF) 2015800300004 EVALUATION BY KONSHIN, BASED ON THE 2015800300005 VALUES OF DE SAUSSURE ET AL.,66PARIS (NUCLEAR DATA 2015800300006 FOR REACTORS),2,233, AND OF HOPKINS AND DIVEN, 2015800300007 NUCL.SCI.ENG.,12(1962)169, IN THE ENERGY RANGE 2015800300008 FROM 40 TO 50 KEV. 2015800300009 PART-DET (N ) NEUTRONS 2015800300010 HISTORY (711217C) 2015800300011 (731005E) 2015800300012 ERR-ANALYS .TOTAL ERROR (SQUARE ROOT OF SUM OF SQUARE(SYSTEMATIC) 2015800300013 AND SQUARE(STATISTICAL)) ARE, 2015800300014 14, 15 AND 18 PER-CENT. 2015800300015 AT 10-20, 20-40 AND 40-50 KEV RESPECTIVELY. 2015800300016 .THE OVERALL TIME RESOLUTION WAS 20 NS/M.AND THE ENERGY2015800300017 RESOLUTION WAS 10 PERCENT AT 30 KEV NEUTRON ENERGY. 2015800300018 ENDBIB 16 0 2015800300019 NOCOMMON 0 0 2015800300020 DATA 4 21 2015800300021 EN-MAX EN-MIN DATA DATA-ERR 2015800300022 MEV MEV NO-DIM NO-DIM 2015800300023 9.0000E-03 8.0000E-03 7.1000E-01 1.2000E-01 2015800300024 1.0000E-02 9.0000E-03 7.1000E-01 1.0000E-01 2015800300025 1.1000E-02 1.0000E-02 6.3000E-01 9.0000E-02 2015800300026 1.2000E-02 1.1000E-02 6.2000E-01 9.0000E-02 2015800300027 1.3000E-02 1.2000E-02 5.2000E-01 8.0000E-02 2015800300028 1.4000E-02 1.3000E-02 5.6000E-01 8.0000E-02 2015800300029 1.5000E-02 1.4000E-02 5.8000E-01 8.0000E-02 2015800300030 1.6000E-02 1.5000E-02 4.7000E-01 7.0000E-02 2015800300031 1.7000E-02 1.6000E-02 4.0000E-01 6.0000E-02 2015800300032 1.8000E-02 1.7000E-02 4.0000E-01 6.0000E-02 2015800300033 1.9000E-02 1.8000E-02 4.0000E-01 6.0000E-02 2015800300034 2.0000E-02 1.9000E-02 4.0000E-01 6.0000E-02 2015800300035 2.2500E-02 2.0000E-02 3.7000E-01 5.0000E-02 2015800300036 2.5000E-02 2.2500E-02 3.2000E-01 5.0000E-02 2015800300037 2.7500E-02 2.5000E-02 3.0000E-01 5.0000E-02 2015800300038 3.0000E-02 2.7500E-02 3.0000E-01 5.0000E-02 2015800300039 3.5000E-02 3.0000E-02 3.1000E-01 5.0000E-02 2015800300040 4.0000E-02 3.5000E-02 2.9000E-01 5.0000E-02 2015800300041 4.5000E-02 4.0000E-02 2.6000E-01 4.0000E-02 2015800300042 5.0000E-02 4.5000E-02 2.5000E-01 4.0000E-02 2015800300043 6.0000E-02 5.0000E-02 2.3000E-01 6.0000E-02 2015800300044 ENDDATA 23 0 2015800300045 ENDSUBENT 44 0 2015800399999 ENDENTRY 3 0 2015899999999