ENTRY 21836 20160208 22472183600000001 SUBENT 21836001 20160208 22472183600100001 BIB 14 40 2183600100002 TITLE Precision determination of gamma-ray energies from the 2183600100003 27Al(n,g) reaction and the level scheme of 28Al 2183600100004 AUTHOR (P.A.Sushkov, V.L.Alexeev, L.P.Kabina, I.A.Kondurov, 2183600100005 D.D.Warner) 2183600100006 INSTITUTE (4RUSFTI,2FR ILL) 2183600100007 REFERENCE (C,81GRENOB,,165,1981) 2183600100008 FACILITY (REAC,2FR ILL) ILL High Flux Reactor 2183600100009 (SPECC) Three-crystal pair-formation spectrometer 2183600100010 INC-SOURCE (REAC) 2183600100011 INC-SPECT Thermal reactor neutron spectrum 2183600100012 SAMPLE No details given 2183600100013 METHOD Gamma spectra measured using a 16384 channel analyser 2183600100014 DETECTOR (GELI) Ge(Li) detector with resolution 1.9 - 5.9 keV 2183600100015 in the energy range 1.4 - 8 MeV 2183600100016 ANALYSIS Spectrum linearization was performed using the 28Al 2183600100017 level scheme and using cubic polynomials for the 2183600100018 channel-energy dependence. 2183600100019 The energy scale was normalised to the following gamma 2183600100020 rays: 2183600100021 4945.319 +0.020 -0.004 keV gamma from 13C decay, 2183600100022 1690.980 +0.004 -0.006 keV gamma from 124Te decay, 2183600100023 and these energies were measured relative to the 2183600100024 411.80441 +/- 0.00108 keV gamma from 198Au decay. 2183600100025 The gamma intensities were calculated from an inner 2183600100026 calibration using the data of Ishaq et al., 1972. 2183600100027 REL-REF (R,,A.F.M.Ishaq+,J,CJP,50,2845,1972) 2183600100028 Data for inner calibration of gamma intensities 2183600100029 ERR-ANALYS (DATA-ERR) Error quoted in reference. To obtain the 2183600100030 total error, the following must be added in 2183600100031 quadrature: 2183600100032 - 9 ppm due to the uncertainty in the energy of the 2183600100033 monitor gamma rays, 2183600100034 - 12 ppm due to the uncertainty in the energy of the 2183600100035 198Au gamma used as a monitor for the monitor 2183600100036 gammas. 2183600100037 HISTORY (19830318C) A.P.T. 2183600100038 (19830322E) 2183600100039 (19830615A) BN. IN SE 002 REACTION SF4 corrected. 2183600100040 (19830801E) 2183600100041 (20160208U) On. Major revision in 002. 2183600100042 ENDBIB 40 0 2183600100043 COMMON 1 3 2183600100044 EN-DUMMY 2183600100045 MILLI-EV 2183600100046 25.3 2183600100047 ENDCOMMON 3 0 2183600100048 ENDSUBENT 47 0 2183600199999 SUBENT 21836002 20160208 22472183600200001 BIB 4 6 2183600200002 REACTION (13-AL-27(N,G)13-AL-28,,SPC,,MXW) 2183600200003 COMMENT The data cover only the most intense gamma rays. 2183600200004 STATUS (TABLE) Table 1 of C,81GRENOB,,165,1981 2183600200005 HISTORY (19830615A) BN. SF4 corrected. 2183600200006 (19830801E) 2183600200007 (20160208A) On. GAM/100N -> PC/REAC 2183600200008 ENDBIB 6 0 2183600200009 NOCOMMON 0 0 2183600200010 DATA 4 44 2183600200011 E E-ERR DATA DATA-ERR 2183600200012 KEV KEV PC/REAC PC/REAC 2183600200013 1.4083E+03 3.0000E-01 9.5000E-01 1.8000E-01 2183600200014 1.5260E+03 8.0000E-02 1.5700E+00 1.4000E-01 2183600200015 1.5896E+03 1.0000E-01 1.2100E+00 1.3000E-01 2183600200016 1.6228E+03 4.0000E-02 4.4000E+00 3.0000E-01 2183600200017 1.9274E+03 5.0000E-02 1.0100E+00 7.0000E-02 2183600200018 1.9838E+03 4.0000E-02 9.3000E-01 6.0000E-02 2183600200019 2.1083E+03 4.0000E-02 2.2300E+00 1.3000E-01 2183600200020 2.1389E+03 2.5000E-02 1.6500E+00 8.0000E-02 2183600200021 2.2717E+03 3.0000E-02 1.4900E+00 9.0000E-02 2183600200022 2.2828E+03 2.0000E-02 3.6300E+00 1.8000E-01 2183600200023 2.5776E+03 3.0000E-02 1.7300E+00 9.0000E-02 2183600200024 2.5902E+03 1.9000E-02 3.3200E+00 1.6000E-01 2183600200025 2.6258E+03 4.0000E-02 1.0900E+00 6.0000E-02 2183600200026 2.7096E+03 6.0000E-02 5.5000E-01 4.0000E-02 2183600200027 2.8214E+03 1.9000E-02 3.2600E+00 1.6000E-01 2183600200028 2.9600E+03 1.5000E-02 8.5000E+00 5.0000E-01 2183600200029 3.0338E+03 1.6000E-02 8.1000E+00 5.0000E-01 2183600200030 3.3030E+03 4.0000E-02 1.1200E+00 5.0000E-02 2183600200031 3.4650E+03 2.3000E-02 7.2000E+00 4.0000E-01 2183600200032 3.5605E+03 4.0000E-02 1.0100E+00 6.0000E-02 2183600200033 3.5911E+03 2.3000E-02 4.7100E+00 2.4000E-01 2183600200034 3.7892E+03 4.0000E-02 1.0200E+00 6.0000E-02 2183600200035 3.8234E+03 5.0000E-02 5.1000E-01 2.0000E-02 2183600200036 3.8490E+03 2.4000E-02 3.2900E+00 1.7000E-01 2183600200037 3.8754E+03 2.4000E-02 2.8000E+00 1.4000E-01 2183600200038 4.0155E+03 4.0000E-02 8.2000E-01 5.0000E-02 2183600200039 4.1334E+03 2.4000E-02 7.3000E+00 4.0000E-01 2183600200040 4.2596E+03 2.0000E-02 7.4000E+00 4.0000E-01 2183600200041 4.4284E+03 9.0000E-02 9.1000E-01 5.0000E-02 2183600200042 4.6601E+03 3.0000E-02 2.8200E+00 1.5000E-01 2183600200043 4.6907E+03 1.8000E-02 4.9100E+00 2.5000E-01 2183600200044 4.7338E+03 3.0000E-02 5.9000E+00 3.0000E-01 2183600200045 4.7645E+03 4.0000E-02 9.7000E-01 5.0000E-02 2183600200046 4.9031E+03 1.9000E-02 3.2700E+00 1.7000E-01 2183600200047 5.1343E+03 2.2000E-02 3.2200E+00 1.6000E-01 2183600200048 5.4109E+03 5.0000E-02 1.9000E+00 1.0000E-01 2183600200049 5.5855E+03 3.0000E-02 1.1700E+00 6.0000E-02 2183600200050 6.1013E+03 2.5000E-02 2.7000E+00 1.4000E-01 2183600200051 6.1980E+03 4.0000E-02 7.1000E-01 4.0000E-02 2183600200052 6.3158E+03 3.0000E-02 2.1600E+00 1.1000E-01 2183600200053 6.4405E+03 4.0000E-02 6.9000E-01 4.0000E-02 2183600200054 6.7105E+03 4.0000E-02 9.4000E-01 5.0000E-02 2183600200055 7.6933E+03 2.5000E-02 3.6800E+00 1.9000E-01 2183600200056 7.7239E+03 2.1000E-02 3.0000E+01 1.5000E+00 2183600200057 ENDDATA 46 0 2183600200058 ENDSUBENT 57 0 2183600299999 ENDENTRY 2 0 2183699999999