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 DATA OUT OF DATE. 2015800100007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