ENTRY 21908 19840926 00002190800000001 SUBENT 21908001 19840926 00002190800100001 BIB 16 45 2190800100002 INSTITUTE (2SWDLND) I.B.,R.Z. 2190800100003 (2SWDTLU) EXPERIMENTAL SITE, A.H.,A.LIN.,L.N. 2190800100004 (2SWDSWR) N.O. 2190800100005 (3YUGNJS) A.LIK. 2190800100006 REFERENCE (J,NP/A,419,(3),509,8405) 2190800100007 (P,KDK-64,27,8308) 2190800100008 (W,LINDHOLM,8406) DATA AND FURTHER INFORMATION GIVEN IN2190800100009 PRIVATE COMMUNICATION. 2190800100010 AUTHOR (I.BERGQVIST,R.ZORRO,A.HAAKANSSON,A.LINDHOLM,L.NILSSON,2190800100011 N.OLSSON,A.LIKAR) 2190800100012 TITLE -THE GIANT ISOVECTOR E2 RESONANCE IN CALCIUM OBSERVED 2190800100013 IN RADIATIVE NEUTRON CAPTURE- 2190800100014 FACILITY (VDGT ,2SWDTLU) 7 MV TANDEM ACCELERATOR. PULSED BEAM 2190800100015 WITH A PULSE WIDTH OF 3 NSEC AND A FREQUENCY OF 2 MHZ.2190800100016 INC-SOURCE (D-T ) TO PRODUCE NEUTRONS WITH ENERGIES ABOVE 20 MEV.2190800100017 (D-D ) TO PRODUCE NEUTRONS WITH ENERGIES BETWEEN 7 2190800100018 AND 14 MEV. 2190800100019 SAMPLE .CYLINDRICAL IN SHAPE, WEIGHING 573 GRAMS. THE SAMPLE 2190800100020 WAS PLACED 14 CM FROM THE GAS CELL WITH ITS AXIS 2190800100021 PERPENDICULAR TO THE (HORISONTAL) REACTION PLANE. 2190800100022 METHOD .GAMMA-RAY SPECTRA RECORDED. 2190800100023 (TOF ) TIME-OF-FLIGHT TECHNIQUES WERE USED TO REDUCE 2190800100024 NEUTRON-INDUCED BACKGROUND IN SPECTRA. THE NEUTRON 2190800100025 INTENSITY FROM THE TARGET WAS ROUTINELY CHECKED BY A 2190800100026 TIME-OF-FLIGHT PLASTIC SCINTILLATOR WHICH WAS 2190800100027 CALIBRATED WITH THE AID OF A POLYETHYLENE TELESCOPE. 2190800100028 DETECTOR (NAICR) A NAI SCINTILLATOR, 23 CM IN DIAMETER AND 21 2190800100029 CM LONG. 2190800100030 ANALYSIS .GAMMA-RAY SPECTRA WERE ENERGY CALIBRATED USING GAMMA 2190800100031 LINES FROM RADIOACTIVE SOURCES AND E.G. THE C-12(N,EL)2190800100032 REACTION WHICH PRODUCES A 15.11 MEV LINE. 2190800100033 COMMENT .SOME OF THE DATA ARE REVISED CROSS SECTIONS FROM THE 2190800100034 REL-REF, PREVIOUSLY COMPILED IN EXFOR21881002. 2190800100035 REL-REF (D,,A.LINDHOLM+,J,NP/A,339,(2),205,8004) 2190800100036 STATUS .DATA TAKEN FROM PRIVATE COMMUNICATION. 2190800100037 HISTORY (840619C) A.L. 2190800100038 (840710E) 2190800100039 CORRECTION .FOR 2190800100040 - ATTENUATION OF NEUTRONS AND GAMMA RAYS IN THE 2190800100041 SAMPLE. 2190800100042 - ANISOTROPHY OF THE NEUTRON FLUX. 2190800100043 ERR-ANALYS (DATA-ERR) THE UNCERTAINTY GIVEN CONSISTS OF THE 2190800100044 STATISTICAL UNCERTAINTY FROM THE UNFOLDING PROCEDURE 2190800100045 AND AN ESTIMATED UNCERTAINTY FROM THE DETECTION 2190800100046 EFFICIANCY AND RESPONSE LINE SHAPE. 2190800100047 ENDBIB 45 0 2190800100048 NOCOMMON 0 0 2190800100049 ENDSUBENT 48 0 2190800199999 SUBENT 21908002 19840710 00002190800200001 BIB 4 6 2190800200002 REACTION (20-CA-40(N,G)20-CA-41,PAR,DA) DIFF. CROSS SECTIONS 2190800200003 AT 90 ADEG FOR CAPTURE TO THE GROUND STATE OF CA-41. 2190800200004 EN-SEC (E-LVL-FIN,20-CA-41) 2190800200005 STATUS .DATA TAKEN FROM PRIVATE COMMUNICATION. 2190800200006 HISTORY (840619C) A.L. 2190800200007 (840710E) 2190800200008 ENDBIB 6 0 2190800200009 COMMON 2 3 2190800200010 E-LVL-FIN ANG 2190800200011 MEV ADEG 2190800200012 0.0000E+00 9.0000E+01 2190800200013 ENDCOMMON 3 0 2190800200014 DATA 3 42 2190800200015 EN DATA DATA-ERR 2190800200016 MEV MU-B/SR MU-B/SR 2190800200017 3.5000E+00 1.9300E+01 2.7000E+00 2190800200018 3.8000E+00 1.4200E+01 2.0000E+00 2190800200019 4.1000E+00 1.1900E+01 1.7000E+00 2190800200020 4.4000E+00 1.2000E+01 1.7000E+00 2190800200021 4.7000E+00 9.2000E+00 1.3000E+00 2190800200022 5.0000E+00 1.0700E+01 1.5000E+00 2190800200023 5.3000E+00 9.1000E+00 1.3000E+00 2190800200024 5.6000E+00 1.0100E+01 1.4000E+00 2190800200025 5.6000E+00 8.5000E+00 1.2000E+00 2190800200026 5.9300E+00 8.0000E+00 1.0000E+00 2190800200027 6.2700E+00 7.3000E+00 9.0000E-01 2190800200028 6.3000E+00 7.4000E+00 1.0000E+00 2190800200029 6.5900E+00 6.6000E+00 9.0000E-01 2190800200030 6.9100E+00 7.3000E+00 1.0000E+00 2190800200031 7.2300E+00 5.5000E+00 7.0000E-01 2190800200032 7.5400E+00 6.6000E+00 9.0000E-01 2190800200033 7.8100E+00 8.0000E+00 1.1000E+00 2190800200034 8.1200E+00 7.8000E+00 1.1000E+00 2190800200035 8.4200E+00 1.1000E+01 1.4000E+00 2190800200036 8.7300E+00 1.1100E+01 1.0000E+00 2190800200037 8.9200E+00 1.3100E+01 1.7000E+00 2190800200038 9.0000E+00 1.1200E+01 1.0000E+00 2190800200039 9.3700E+00 1.6200E+01 2.2000E+00 2190800200040 9.5000E+00 1.3700E+01 1.2000E+00 2190800200041 1.0000E+01 1.6000E+01 1.4000E+00 2190800200042 1.0500E+01 1.5200E+01 1.3000E+00 2190800200043 1.1000E+01 1.5400E+01 1.3000E+00 2190800200044 1.2000E+01 1.4400E+01 1.2000E+00 2190800200045 1.3000E+01 1.3800E+01 1.2000E+00 2190800200046 1.3500E+01 1.0900E+01 1.0000E+00 2190800200047 1.4000E+01 1.3200E+01 1.2000E+00 2190800200048 2.0160E+01 3.1500E+00 6.3000E-01 2190800200049 2.0790E+01 3.5400E+00 4.8000E-01 2190800200050 2.1990E+01 3.1400E+00 4.8000E-01 2190800200051 2.3130E+01 2.0700E+00 4.0000E-01 2190800200052 2.4240E+01 2.0100E+00 4.4000E-01 2190800200053 2.4770E+01 1.6600E+00 4.0000E-01 2190800200054 2.5320E+01 2.3900E+00 4.0000E-01 2190800200055 2.5850E+01 1.9100E+00 5.6000E-01 2190800200056 2.6380E+01 9.5000E-01 5.6000E-01 2190800200057 2.6900E+01 1.2200E+00 5.7000E-01 2190800200058 2.7430E+01 9.9000E-01 5.5000E-01 2190800200059 ENDDATA 44 0 2190800200060 ENDSUBENT 59 0 2190800299999 ENDENTRY 2 0 2190899999999