ENTRY 12815 19861209 00001281500000001 SUBENT 12815001 19861209 00001281500100001 BIB 14 34 1281500100002 INSTITUTE (1USAMHG) 1281500100003 REFERENCE (J,NSE,94,227,8611) 1281500100004 (T,GRADY,81) 1281500100005 AUTHOR (D.J.GRADY,G.F.KNOLL,J.C.ROBERTSON) 1281500100006 TITLE ABSOLUTE MEASUREMENTS OF THE 115-IN (N,GAMMA) 116M1-IN 1281500100007 CROSS-SECTION FOR FAST NEUTRONS. 1281500100008 FACILITY (CYCLO) 1281500100009 METHOD (ACTIV) CLOSEST FOIL SPACING IS 3. MM FROM NEUTRON 1281500100010 SOURCE. 1281500100011 (MANGB) NEUTRON SOURCE STRENGTHS DETERMINED IN A 1281500100012 MANGANESE BATH 1281500100013 MONITOR (98-CF-252(0,F),,NU) A TERTIARY STANDARD CALIBRATED 1281500100014 AGAINST NBS-II 1281500100015 DECAY-DATA (49-IN-116-M1,54.12MIN) 1281500100016 DETECTOR (PROPC) 4*PI BETA GAS FLOW PROPORTIONAL COUNTER 1281500100017 USING 90 PERCENT ARGON AND 10 PERCENT METHANE. 1281500100018 SAMPLE 8 FOILS OF METALLIC INDIUM WITH BETTER THAN 99.999 1281500100019 PERCENT PURITY. THE FOILS WERE 1.922 CM DIAMETER 1281500100020 AND .0067 CM THICK. SEVEN FOILS WERE MOUNTED WITH 1281500100021 ALUMINUM SPACERS IN A SANDWICH 10.16 CM THICK. 1281500100022 CORRECTION DATA WERE CORRECTED FOR NEUTRON SCATTERING FROM THE 1281500100023 STRUCTURES, ROOM-SCATTERED NEUTRONS AND NEUTRON 1281500100024 SCATTERING FROM THE FOIL HOLDER. 1281500100025 ERR-ANALYS (ERR-T) TOTAL UNCERTAINTY WITH THE FOLLOWING MAJOR 1281500100026 COMPONENTS: 1281500100027 (DATA-ERR1) NEUTRON SOURCE CALIBRATION 1281500100028 (DATA-ERR2) FLUX CALCULATIONS 1281500100029 (DATA-ERR3) ACTIVITY MEASUREMENT 1281500100030 (DATA-ERR4) SPECTRUM CORRECTION 1281500100031 STATUS (APRVD) G.F.KNOLL, 86/12/23. 1281500100032 HISTORY (830520C) 1281500100033 (860613A) BIB UPDATES. 1281500100034 (861209A) UPDATED AS PER NUC.SCI.ENG.94,227(1986) 1281500100035 SPECTRUM AVERAGED VALUES REMOVED. 1281500100036 ENDBIB 34 0 1281500100037 COMMON 1 3 1281500100038 DATA-ERR3 1281500100039 PER-CENT 1281500100040 1.4 1281500100041 ENDCOMMON 3 0 1281500100042 ENDSUBENT 41 0 1281500199999 NOSUBENT 12815002 19861209 00001281500200001 SUBENT 12815003 19861209 00001281500300001 BIB 3 7 1281500300002 REACTION (49-IN-115(N,G)49-IN-116-M1,M+,SIG) 1281500300003 INC-SOURCE (PHOTO) SB-BE SOURCE ACTIVATED IN FORD REACTOR TO 1281500300004 A SOURCE STRENGTH OF 2.319X10**7 NEUTRONS/SEC 1281500300005 AT THE BEGINNING OF FOIL ACTIVATION. 1281500300006 ANALYSIS CORRECTED FOR SPECTRUM EFFECTS USING ENDF/B-V 1281500300007 EVALUATION FOR CROSS SECTION SHAPE. 1281500300008 SPECTRUM AVERAGED CROSS-SECTION=592 MB. 1281500300009 ENDBIB 7 0 1281500300010 NOCOMMON 0 0 1281500300011 DATA 6 1 1281500300012 EN DATA ERR-T DATA-ERR1 DATA-ERR2 DATA-ERR4 1281500300013 KEV MB PER-CENT PER-CENT PER-CENT PER-CENT 1281500300014 23. 588. 1.9 0.7 1.2 0.1 1281500300015 ENDDATA 3 0 1281500300016 ENDSUBENT 15 0 1281500399999 NOSUBENT 12815004 19861209 00001281500400001 SUBENT 12815005 19861209 00001281500500001 BIB 4 8 1281500500002 REACTION (49-IN-115(N,G)49-IN-116-M1,M+,SIG) 1281500500003 INC-SOURCE (PHOTO) NA-D(2)C SOURCE ACTIVATED IN FORD REACTOR TO 1281500500004 A SOURCE STRENGTH OF 1.686X10**7 NEUTRONS/SEC 1281500500005 AT THE BEGINNING OF FOIL ACTIVATION. 1281500500006 ANALYSIS CORRECTED FOR SPECTRUM EFFECTS USING ENDF/B-V 1281500500007 EVALUATION FOR CROSS SECTION SHAPE. 1281500500008 SPECTRUM AVERAGED CROSS-SECTION=206 MB. 1281500500009 STATUS (DEP,12815004) 1281500500010 ENDBIB 8 0 1281500500011 NOCOMMON 0 0 1281500500012 DATA 6 1 1281500500013 EN DATA ERR-T DATA-ERR1 DATA-ERR2 DATA-ERR4 1281500500014 KEV MB PER-CENT PER-CENT PER-CENT PER-CENT 1281500500015 265. 196. 2.0 0.7 1.1 0.6 1281500500016 ENDDATA 3 0 1281500500017 ENDSUBENT 16 0 1281500599999 NOSUBENT 12815006 19861209 00001281500600001 SUBENT 12815007 19861209 00001281500700001 BIB 4 8 1281500700002 REACTION (49-IN-115(N,G)49-IN-116-M1,M+,SIG) 1281500700003 INC-SOURCE (PHOTO) LA-BE SOURCE ACTIVATED IN FORD REACTOR TO 1281500700004 A SOURCE STRENGTH OF 1.353X10**6 NEUTRONS/SEC 1281500700005 AT THE BEGINNING OF FOIL ACTIVATION. 1281500700006 ANALYSIS CORRECTED FOR SPECTRUM EFFECTS USING ENDF/B-V 1281500700007 EVALUATION FOR CROSS SECTION SHAPE. 1281500700008 SPECTRUM AVERAGED CROSS-SECTION=281 MB. 1281500700009 STATUS DATA TAKEN FROM ANL-83-4,179(1982). 1281500700010 ENDBIB 8 0 1281500700011 NOCOMMON 0 0 1281500700012 DATA 3 1 1281500700013 EN DATA ERR-T 1281500700014 KEV MB PER-CENT 1281500700015 770. 288. 3.59 1281500700016 ENDDATA 3 0 1281500700017 ENDSUBENT 16 0 1281500799999 NOSUBENT 12815008 19861209 00001281500800001 SUBENT 12815009 19861209 00001281500900001 BIB 3 7 1281500900002 REACTION (49-IN-115(N,G)49-IN-116-M1,M+,SIG) 1281500900003 INC-SOURCE (PHOTO) NA-BE SOURCE ACTIVATED IN FORD REACTOR TO 1281500900004 A SOURCE STRENGTH OF 4.759X10**7 NEUTRONS/SEC 1281500900005 AT THE BEGINNING OF FOIL ACTIVATION. 1281500900006 ANALYSIS CORRECTED FOR SPECTRUM EFFECTS USING ENDF/B-V 1281500900007 EVALUATION FOR CROSS SECTION SHAPE. 1281500900008 SPECTRUM AVERAGED CROSS-SECTION=203 MB. 1281500900009 ENDBIB 7 0 1281500900010 NOCOMMON 0 0 1281500900011 DATA 6 1 1281500900012 EN DATA ERR-T DATA-ERR1 DATA-ERR2 DATA-ERR4 1281500900013 KEV MB PER-CENT PER-CENT PER-CENT PER-CENT 1281500900014 964. 203. 1.8 0.9 0.8 0.0 1281500900015 ENDDATA 3 0 1281500900016 ENDSUBENT 15 0 1281500999999 ENDENTRY 9 0 1281599999999