ENTRY 20279 19840409 00002027900000001 SUBENT 20279001 19840409 00002027900100001 BIB 12 29 2027900100002 INSTITUTE (2JPNKTO) RESEARCH REACTOR INST. 2027900100003 (2JPNJAE) ADDRESS FOR THE LAST 2 AUTHORS. 2027900100004 REFERENCE (J,JNE,27,741,7310) 2027900100005 ((P,INDC(JAP)-13,36,7208)=(P,EANDC(J)-26,36,7208))GRAPH2027900100006 AUTHOR (K.KOBAYASHI, I.KIMURA, H.GOTOH, H.YAGI) 2027900100007 TITLE -MEASUREMENT OF THE CROSS-SECTION FOR THE 2027900100008 IN-115(N,N')IN-115M REACTION.- 2027900100009 FACILITY (VDG ) 2 MEV VAN DE GRAAFF ACCELERATOR AT JAERI. 2027900100010 INC-SOURCE (D-D ) D(D,N)HE3 REACTION. 2027900100011 INC-SPECT NEUTRON ENERGY WAS CALCULATED WITH KINEMATIC (BROLLEY,2027900100012 FOWLER,FAST N-PHYSICS,I,P.73,INTERSCIENCE,N.Y.) OF 2027900100013 REACTION FROM DEUTERON ENERGY CONSIDERING ENERGY LOSS 2027900100014 IN NICKEL FOIL AND GAS TARGET AND ANGULAR SPREAD. 2027900100015 METHOD (ACTIV) ACTIVATION. 2027900100016 DETECTOR (NAICR) 3 IN. DIAM. * 3 IN. NAI(TL) SCINTILLATION 2027900100017 COUNTER. PHOTOPEAK EFFICIENCY WAS CALIBRATED WITH 2027900100018 STANDARD GAMMA SOURCES FROM IAEA. 2027900100019 .PROTON RECOIL COUNTER FOR NEUTRON-FLUX MEASUREMENT. 2027900100020 MONITOR .ABSOLUTE, NEUTRON FLUX WAS DETERMINED 2027900100021 ABSOLUTELY WITH A PAIR OF SEMI-CONDUCTOR PROTON RECOIL2027900100022 COUNTERS. 2027900100023 HISTORY (731025C) 2027900100024 (740626E) 2027900100025 (840106U) A.P.T. JAPAN CODE CHANGED TO JPN 2027900100026 (840106E) 2027900100027 ERR-ANALYS QUADRATIC SUM OF DIFFERENT ERROR SOURCES, TOTAL ERROR 2027900100028 OF 3.7 TO 4.0 PERCENT. MOREOVER, UNCERTAINTY OF ABOUT2027900100029 2 PERCENT IN THE INTERNAL CONVERSION COEFFICIENT OF 2027900100030 IN-115M.(LEDERER ET AL.,TABLE OF ISOTOPES,6TH ED,1967)2027900100031 ENDBIB 29 0 2027900100032 NOCOMMON 0 0 2027900100033 ENDSUBENT 32 0 2027900199999 SUBENT 20279002 19831122 00002027900200001 BIB 5 7 2027900200002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG) 2027900200003 PART-DET (DG ) DECAY GAMMAS. 2027900200004 STATUS .FROM TABLE 1 OF J.NUCL.ENERGY 27,741. 2027900200005 HISTORY (731025C) 2027900200006 (740626E) 2027900200007 CORRECTION CONTRIBUTION OF BACKGROUND NEUTRONS WAS CONFIRMED TO 2027900200008 BE NEGLIGIBLE SMALL. 2027900200009 ENDBIB 7 0 2027900200010 COMMON 1 3 2027900200011 HL 2027900200012 HR 2027900200013 4.5000E+00 2027900200014 ENDCOMMON 3 0 2027900200015 DATA 4 10 2027900200016 EN EN-RSL DATA DATA-ERR 2027900200017 MEV MEV B B 2027900200018 3.3700E+00 1.6000E-02 3.4600E-01 1.3000E-02 2027900200019 3.4200E+00 1.6000E-02 3.5100E-01 1.4000E-02 2027900200020 3.5200E+00 1.7000E-02 3.3900E-01 1.3000E-02 2027900200021 3.8000E+00 1.5000E-02 3.3200E-01 1.3000E-02 2027900200022 3.8000E+00 1.6000E-02 3.3300E-01 1.3000E-02 2027900200023 3.9500E+00 1.6000E-02 3.1400E-01 1.2000E-02 2027900200024 4.1700E+00 1.8000E-02 3.3400E-01 1.3000E-02 2027900200025 4.5400E+00 1.1000E-02 3.2800E-01 1.3000E-02 2027900200026 4.5900E+00 1.8000E-02 3.1700E-01 1.2000E-02 2027900200027 4.8900E+00 2.4000E-02 3.1400E-01 1.2000E-02 2027900200028 ENDDATA 12 0 2027900200029 ENDSUBENT 28 0 2027900299999 SUBENT 20279003 19831122 00002027900300001 BIB 7 14 2027900300002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG,,FIS) 2027900300003 INC-SOURCE (REAC ) THERMAL NEUTRON FACILITY OF THE KYOTO 2027900300004 UNIVERSITY REACTOR. 2027900300005 METHOD .MEASURED WITH A FISSION PLATE OF 90 PERCENT ENRICHED 2027900300006 URANIUM. 2027900300007 PART-DET (DG ) DECAY GAMMAS. 2027900300008 COMMENT .A CALCULATION WAS PERFORMED FOR COMPARISON WITH 2027900300009 EXPERIMENTAL VALUE, GIVING 176 MB. A MAXWELLIAN 2027900300010 FISSION SPECTRUM WAS USED. DATA FOR ENERGY REGION NOT 2027900300011 COVERED BY THIS EXPERIMENT WAS TAKEN FROM BUTLER AND 2027900300012 SANTRY, BULL.AM.PHYS.SOC.12,547. 2027900300013 STATUS .FROM TABLE 3 OF J.NUCL.ENERGY 27,741. 2027900300014 HISTORY (740605L) 2027900300015 (740626E) 2027900300016 ENDBIB 14 0 2027900300017 NOCOMMON 0 0 2027900300018 DATA 4 1 2027900300019 EN-DUMMY HL DATA DATA-ERR 2027900300020 MEV HR B B 2027900300021 1.0000E+00 4.2000E+00 1.7500E-01 6.0000E-03 2027900300022 ENDDATA 3 0 2027900300023 ENDSUBENT 22 0 2027900399999 ENDENTRY 3 0 2027999999999