ENTRY 21819 19830801 00002181900000001
SUBENT 21819001 19830801 00002181900100001
BIB 15 83 2181900100002
INSTITUTE (2SWDLND) UNIVERSITY OF LUND. 2181900100003
REFERENCE (C,82ANTWER,,866,8209) 2181900100004
AUTHOR (P.ANDERSSON,R.ZORRO,I.BERQVIST) 2181900100005
TITLE -ON NEUTRON CAPTURE CROSS SECTION MEASUREMENTS 2181900100006
WITH THE ACTIVATION TECHNIQUE IN THE MEV 2181900100007
REGION.- 2181900100008
FACILITY (VDG,2SWDLND) 3 MV TANDEM VAN DE GRAAFF. 2181900100009
INC-SOURCE (P-T ) PROTON-TRITIUM REACTION AND 2181900100010
(D-T ) DEUTERON-TRITIUM REACTION. 2181900100011
THE PROTONS AND THE DEUTERONS WERE ACCELERATED 2181900100012
BY THE VAN DE GRAAFF MACHINE. 2181900100013
SEVERAL TARGETS WERE USED AND INVESTIGATED WITH 2181900100014
RESPECT TO THE PRIMARY NEUTRON BACKGROUND. 2181900100015
- THIN TITANIUM LAYERS, ABOUT 2 MG/CM**2 2181900100016
THICKNESS IN WHICH THE DEUTERIUM OR TRITIUM 2181900100017
WAS ABSORBED, EAVAPORATED ONTO A 0.5 MM 2181900100018
THICK BACKING. IT WAS SHOWN THAT THE TI(T) 2181900100019
CANNOT BE USED ANYMORE BEYOND 4.5 MEV 2181900100020
NEUTRON ENERGY, AND THAT DEUTERIUM TARGETS 2181900100021
ARE PREFERABLE ABOVE 3.0 MEV. THE ENERGY 2181900100022
RANGE CAN THAN BE EXTENDED BY 1. MEV. 2181900100023
- DEUTERIUM GAS TARGET WITH A 4.2 MG/CM**2 2181900100024
THICK MO-FOIL AS ENTRANCE WINDOW AND GOLD 2181900100025
AS A BEAM STOP. THIS WAY THE NEUTRON ENERGY 2181900100026
RANGE CAN BE EXTENDED BY SEVERAL MEV. 2181900100027
- ALSO A T(ZR-90) TARGET WITH NATURAL ZR 2181900100028
HAS BEEN TESTED. 2181900100029
SAMPLE .PLACED AT DISTANCES SUCH THAT THE SOLID ANGLE 2181900100030
SUBTENDED BY THE SAMPLES AT THE TARGET WAS THE 2181900100031
SAME IN ALL CASES. FOR THE STUDIES OF THE 2181900100032
THICKNESS DEPENDENCE OF THE ACTIVATION YIELDS, 2181900100033
INDIUM SAMPLES WERE USED WITH A DIAMETER OF 10. 2181900100034
MM AND A THICKNESS RANGING FROM 0.18 TO 1.66 2181900100035
GRAMS/CM**2. THE TARGET-SAMPLE DISTANCE DEPENDENCE 2181900100036
WAS DETERMINED USING 0.6 GRAMS/CM**2 SAMPLES WITH 2181900100037
DIAMETERS RANGING FROM 5.0 TO 20. MM. 2181900100038
METHOD .ACTIVATION. 2181900100039
.DEPENDENCE OF THE ACTIVATION YIELDS ON SAMPLE 2181900100040
THICKNESS AND EFFECTIVE TARGET-SAMPLE DISTANCE 2181900100041
HAS BEEN INVESTIGATED TO ALLOW DETAILED 2181900100042
CORRECTIONS. 2181900100043
DETECTOR (LONGC) TO MONITOR THE NEUTRON FLUX. AT 1.2 M 2181900100044
FROM THE TARGET. 2181900100045
(GELI ) 80 CC OPEN END GE(LI) DETECTOR. THE 2181900100046
RELATIVE EFFICIENCY WAS DETERMINED WITH A 2181900100047
EU-152 SOURCE. 2181900100048
MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG) 2181900100049
PART-DET (DG ) DECAY-GAMMAS. 2181900100050
STATUS .DATA TAKEN FROM MAIN REFERENCE. 2181900100051
HISTORY (830121C) G.C. 2181900100052
(830210E) 2181900100053
(830314A) A.P.T. UNITS IN SUBWORK 002 CORRECTED. 2181900100054
(830322E) 2181900100055
(830610A) BN. ABUNDANCE IN SE 002 CORRECTED. 2181900100056
(830801E) 2181900100057
CORRECTION .PRIMARY NEUTRON BACKGROUND, I.E. NEUTRONS 2181900100058
PRODUCED BY (P,N) AND (D,N) REACTIONS IN THE 2181900100059
TARGET BACKING AND ABSORPTION MATERIALS AND 2181900100060
IN THE APERTURES ALONG THE BEAM LINE. THIS WAS 2181900100061
DONE BY USING TARGETS WITH NATURAL HYDROGEN 2181900100062
IN STEAD OF D OR T. (EMPTY TARGETS). 2181900100063
.SECONDARY NEUTRON BACKGROUND. IT CONSISTS OF 2181900100064
SEVERAL CONTRIBUTIONS , 2181900100065
- NEUTRONS PRODUCED BY INELASTIC SCATTERING 2181900100066
IN THE SAMPLE. THIS WAS CORRECTED FOR BY 2181900100067
STUDYING THE ACTIVATION YIELD AS A FUNCTION 2181900100068
OF THE SAMPLE THICKNESS. 2181900100069
- NEUTRONS PRODUCED BY INELASTIC SCATTERING 2181900100070
IN STRUCTURAL MATERIALS NEAR THE TARGET- 2181900100071
SAMPLE ASSEMBLY AND NEUTRONS SCATTERED BY 2181900100072
THE WALLS OF THE ROOM. THIS WAS CORRECTED 2181900100073
FOR BY THE STUDYING THE ACTIVATION YIELD 2181900100074
AS A FUNCTION OF THE TARGET-SAMPLE DISTANCE. 2181900100075
BOTH EFFECTS PRODUCE NEUTRONS WITH LOWER 2181900100076
ENERGIES WITH HIGHER (N,G) CROSS SECTIONS 2181900100077
AND ARE THUS IMPORTANT. 2181900100078
ERR-ANALYS (ERR-T) TOTAL ERROR GIVEN. 2181900100079
IT CONSISTS OF THE FOLLOWING CONTRIBUTIONS , 2181900100080
(ERR-S) STATISTICAL UNCERTAINTIES , 4-5 PERC. 2181900100081
(MONIT-ERR) 6 PERCENT. 2181900100082
(ERR-1) RELATIVE DETECTION EFFICIENCY, 2 PERC. 2181900100083
(ERR-2) GAMMA-RAY CORRECTION FACTORS, 2 PERC. 2181900100084
(ERR-3) DECAY- AND BRANCHING RATIOS, 2 PERC. 2181900100085
ENDBIB 83 0 2181900100086
COMMON 4 3 2181900100087
ERR-S ERR-1 ERR-2 ERR-3 2181900100088
PER-CENT PER-CENT PER-CENT PER-CENT 2181900100089
5.0000E+00 2.0000E+00 2.0000E+00 2.0000E+00 2181900100090
ENDCOMMON 3 0 2181900100091
ENDSUBENT 90 0 2181900199999
SUBENT 21819002 19861015 00002181900200001
BIB 5 14 2181900200002
REACTION (49-IN-115(N,G)49-IN-116-M1,M+,SIG) 2181900200003
DECAY-DATA (49-IN-116-M1,3247.SEC,DG,1293.54,0.85) 2181900200004
DECAY-MON (49-IN-115-M,16150.SEC,DG,336.0,0.459) 2181900200005
STATUS .DATA TAKEN FROM TABLE 2 OF MAIN REFERENCE. 2181900200006
THE UNITS OF THE INCIDENT NEUTRON ENERGY ARE 2181900200007
MISPRINTED AS 'KEV' INSTEAD OF 'MEV'. 2181900200008
HISTORY (830121C) G.C. 2181900200009
(830210E) 2181900200010
(830314A) A.P.T. NEUTRON ENERGY UNIT HEADING CORRECTED.2181900200011
(830322E) 2181900200012
(830610A) BN. ABUNDANCE CORRECTED 2181900200013
(830801E) 2181900200014
(860808A)HH REACTION/DECAY DATA STRING CORRECTED 2181900200015
(860807E) 2181900200016
ENDBIB 14 0 2181900200017
NOCOMMON 0 0 2181900200018
DATA 5 17 2181900200019
EN DATA ERR-T MONIT MONIT-ERR 2181900200020
MEV MB PER-CENT MB PER-CENT 2181900200021
1.9600E+00 1.3200E+02 6.8000E+00 2.6200E+02 6.1000E+00 2181900200022
2.0600E+00 1.3200E+02 6.9000E+00 2.8700E+02 6.1000E+00 2181900200023
2.1600E+00 1.2600E+02 6.8000E+00 3.1300E+02 6.0000E+00 2181900200024
2.2100E+00 1.2700E+02 6.8000E+00 3.1900E+02 6.0000E+00 2181900200025
2.2600E+00 1.1900E+02 6.8000E+00 3.2300E+02 6.0000E+00 2181900200026
2.3500E+00 1.0200E+02 6.8000E+00 3.3000E+02 6.0000E+00 2181900200027
2.4500E+00 7.5400E+01 6.7000E+00 3.3600E+02 6.0000E+00 2181900200028
2.6800E+00 6.0000E+01 6.9000E+00 3.4300E+02 6.0000E+00 2181900200029
2.9300E+00 4.7000E+01 6.9000E+00 3.4800E+02 6.0000E+00 2181900200030
3.1700E+00 3.9000E+01 8.2000E+00 3.4800E+02 7.3000E+00 2181900200031
3.4200E+00 3.2900E+01 8.1000E+00 3.4100E+02 7.3000E+00 2181900200032
3.6800E+00 2.6300E+01 7.7000E+00 3.3600E+02 6.0000E+00 2181900200033
3.8600E+00 2.2400E+01 7.7000E+00 3.2800E+02 6.0000E+00 2181900200034
4.0600E+00 2.0400E+01 8.0000E+00 3.2700E+02 6.0000E+00 2181900200035
4.2100E+00 1.7300E+01 8.0000E+00 3.2500E+02 6.0000E+00 2181900200036
4.3600E+00 1.5500E+01 7.9000E+00 3.2100E+02 6.0000E+00 2181900200037
4.4600E+00 1.3200E+01 1.5200E+01 3.2100E+02 6.0000E+00 2181900200038
ENDDATA 19 0 2181900200039
ENDSUBENT 38 0 2181900299999
ENDENTRY 2 0 2181999999999