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