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