ENTRY 20235 19831121 00002023500000001
SUBENT 20235001 19831121 00002023500100001
BIB 14 27 2023500100002
INSTITUTE (2NEDRCN) 2023500100003
REFERENCE (J,PHY,38,48,6806) 2023500100004
AUTHOR (E.R.REDDINGIUS, J.F.M.POTTERS, H.POSTMA) 2023500100005
TITLE - A STUDY OF GAMMA-RAY SPECTRA OF THERMAL NEUTRON 2023500100006
CAPTURE IN ND-143 AND ND-145, INCLUDING DIRECTIONAL 2023500100007
ANISOTROPY AND LINEAR POLARIZATION MEASUREMENTS OF 2023500100008
SUCH GAMMA RAYS FROM ALIGNED ND-143 NUCLEI - 2023500100009
FACILITY .HIGH FLUX REACTOR AT PETTEN. 2023500100010
INC-SOURCE .REFLECTION ON A CU-MONOCRYSTAL YIELDED A 48 MILLI-EV 2023500100011
MONOENERGETIC NEUTRON BEAM. 2023500100012
SAMPLE .SAMPLES ENRICHED IN ND-143 AND ND-145 USED, 2023500100013
DETAILS GIVEN IN TABLE 1 OF PHYSICA,38(1968)48. 2023500100014
DETECTOR (GELI ) 5 CM**3 GE(LI)-DETECTOR. 2023500100015
MONITOR (60-ND-0(N,G),,SPC) 2023500100016
.ABOVE 4 MEV NORMALIZED TO THE SUM OF THE 6256 AND 2023500100017
6505 KEV GAMMA LINES (= 13.4 GAMMAS/100 NEUTRONS). 2023500100018
.BELOW 2 MEV NORMALIZED TO THE SUM OF THE 616 AND 2023500100019
696 KEV GAMMA LINES. 2023500100020
PART-DET (G ) GAMMAS 2023500100021
COMMENT .A COMPILATION OF E2-M1 MIXING RATIOS FOR 2+ TO 2+ 2023500100022
TRANSITIONS FOR NUCLEI WITH A=18 TO A=212 IS GIVEN 2023500100023
IN TABLE 6 OF PHYSICA,38(1968)48. 2023500100024
STATUS .DATA FROM PHYSICA,38(1968)48. 2023500100025
HISTORY (721003C) 2023500100026
(740521E) 2023500100027
ERR-ANALYS .STATISTICAL ERROR GIVEN, ERROR DUE TO NORMALIZATION 2023500100028
NOT INCLUDED. 2023500100029
ENDBIB 27 0 2023500100030
COMMON 1 3 2023500100031
EN 2023500100032
MEV 2023500100033
4.8000E-08 2023500100034
ENDCOMMON 3 0 2023500100035
ENDSUBENT 34 0 2023500199999
SUBENT 20235002 19831121 00002023500200001
BIB 2 3 2023500200002
REACTION (60-ND-143(N,G)60-ND-144,,SPC) 2023500200003
HISTORY (721003C) 2023500200004
(740521E) 2023500200005
ENDBIB 3 0 2023500200006
NOCOMMON 0 0 2023500200007
DATA 5 16 2023500200008
E E-ERR DATA DATA-ERR DATA-MAX 2023500200009
MEV MEV GAM/100N GAM/100N GAM/100N 2023500200010
6.1600E-01 2.7000E+01 3.0000E+00 2023500200011
6.9600E-01 6.3000E+01 6.0000E+00 2023500200012
8.1400E-01 8.0000E+00 8.0000E-01 2023500200013
8.6400E-01 7.5000E+00 8.0000E-01 2023500200014
9.8000E-01 1.3000E+00 2.0000E-01 2023500200015
1.4300E+00 3.3000E+00 5.0000E-01 2023500200016
4.6800E+00 1.0000E+00 2.0000E-01 2023500200017
4.7900E+00 1.1000E+00 2.0000E-01 2023500200018
4.9550E+00 1.0000E+00 2.0000E-01 2023500200019
5.4400E+00 2.2000E+00 2.0000E-01 2023500200020
5.5250E+00 1.5000E+00 2.0000E-01 2023500200021
5.6390E+00 3.0000E-01 3.0000E-02 2023500200022
5.7080E+00 5.0000E-01 5.0000E-02 2023500200023
6.2560E+00 5.0000E-03 4.0000E+00 2.0000E-01 2023500200024
6.5050E+00 5.0000E-03 9.4000E+00 4.0000E-01 2023500200025
7.1210E+00 8.0000E-03 2023500200026
ENDDATA 18 0 2023500200027
ENDSUBENT 26 0 2023500299999
SUBENT 20235003 19831121 00002023500300001
BIB 2 3 2023500300002
REACTION (60-ND-145(N,G)60-ND-146,,SPC) 2023500300003
HISTORY (721003C) 2023500300004
(740521E) 2023500300005
ENDBIB 3 0 2023500300006
NOCOMMON 0 0 2023500300007
DATA 4 16 2023500300008
E E-ERR DATA DATA-ERR 2023500300009
MEV MEV GAM/100N GAM/100N 2023500300010
4.5500E-01 4.9000E+01 1.1000E+01 2023500300011
4.7000E-01 2.7000E+00 6.0000E-01 2023500300012
5.9000E-01 1.5000E+01 3.0000E+00 2023500300013
1.0400E+00 1.8000E+00 4.0000E-01 2023500300014
1.3400E+00 1.7000E+00 4.0000E-01 2023500300015
1.4800E+00 1.9000E+00 4.0000E-01 2023500300016
4.4200E+00 3.0000E-01 1.0000E-01 2023500300017
5.0200E+00 5.0000E-01 2.0000E-01 2023500300018
5.0500E+00 4.0000E-01 2.0000E-01 2023500300019
5.2100E+00 3.0000E-01 1.0000E-01 2023500300020
5.6000E+00 1.0000E-01 2.0000E-02 2023500300021
5.6500E+00 5.0000E-01 1.0000E-01 2023500300022
5.8000E+00 1.0000E+00 2.0000E-01 2023500300023
6.0950E+00 3.5000E+00 4.0000E-01 2023500300024
6.5200E+00 5.0000E-03 1.3000E+00 3.0000E-01 2023500300025
7.1100E+00 5.0000E-03 3.6000E+00 4.0000E-01 2023500300026
ENDDATA 18 0 2023500300027
ENDSUBENT 26 0 2023500399999
ENDENTRY 3 0 2023599999999