ENTRY 20317 19860411 00002031700000001 SUBENT 20317001 19860411 00002031700100001 BIB 13 39 2031700100002 INSTITUTE (2JPNKTO) 2031700100003 REFERENCE (J,NST,8,59,7102) 2031700100004 (R,EUR-5667,(2),142,75) REVIEW WITH SAME DATA. 2031700100005 (C,71VIENNA,,113,7108) FISSION PLATE DATA. 2031700100006 (P,EANDC(J)-19L,26,7008) ABST. SUPERSEDED. 2031700100007 (P,EANDC(J)-13L,23,6908) ABST. SUPERSEDED. 2031700100008 AUTHOR (I.KIMURA, K.KOBAYASHI, T.SHIBATA) 2031700100009 TITLE -MEASUREMENTS OF AVERAGE CROSS SECTIONS FOR SOME 2031700100010 THRESHOLD REACTIONS FOR NEUTRONS WITH FISSION-TYPE 2031700100011 REACTOR SPECTRUM- 2031700100012 FACILITY (REAC ) KYOTO UNIVERSITY RESEARCH REACTOR, KUR. 2031700100013 5 MEGA-WATT, THERMAL REACTOR. NEUTRON SPECTRUM 2031700100014 ABOVE 1.5 MEV IS VERY CLOSE TO A FISSION NEUTRON 2031700100015 SPECTRUM. THERE ARE HOWEVER MANY THERMAL NEUTRONS. 2031700100016 INC-SPECT .U-235 FISSION NEUTRON SPECTRUM. 2031700100017 METHOD (ACTIV) ACTIVATION. 2031700100018 DETECTOR (GELI ) GE(LI) CALIBRATED BY IAEA STANDARD SOURCES. 2031700100019 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG,,FIS) 2031700100020 ((MONIT2)28-NI-58(N,P)27-CO-58,,SIG,,FIS) 2031700100021 THE VALUES OF THE FAST NEUTRON FLUX 2031700100022 MEASURED WITH THESE MONITORS AGREE 2031700100023 WITH EACH OTHER WITHIN 3 PERCENT FOR THE 2031700100024 FISSION SPECTRUM (FISSION PLATE) AND 2031700100025 WITHIN 2 PERCENT FOR THE FAST REACTOR 2031700100026 SPECTRUM. 2031700100027 DECAY-MON (11-NA-24-G,15.HR,DG,1370.,1.0) 2031700100028 (27-CO-58-G,71.3D,DG,810.,0.99) 2031700100029 STATUS .DATA FROM NUCL.SCI.TECHN.8,59. 2031700100030 HISTORY (711010C) 2031700100031 (740626E) 2031700100032 (800722A) NEW REFERENCE AND FACILITY ADDED. 2031700100033 (800808E) 2031700100034 (840106U) A.P.T. JAPAN CODE CHANGED TO JPN 2031700100035 (840106E) 2031700100036 (860227A)N.CH 2031700100037 (860411E) 2031700100038 ERR-ANALYS .STATISTICAL ERROR, UNCERTAINTY IN MONITORING THE 2031700100039 NEUTRON FLUX, SYSTEMATIC ERROR ABOUT 5 PERCENT. 2031700100040 .DETAILED DISCUSSION IN REFERENCE. 2031700100041 ENDBIB 39 0 2031700100042 COMMON 3 3 2031700100043 EN-DUMMY MONIT1 MONIT2 2031700100044 MEV MB MB 2031700100045 1.5000E+00 6.4400E-01 1.0200E+02 2031700100046 ENDCOMMON 3 0 2031700100047 ENDSUBENT 46 0 2031700199999 SUBENT 20317002 19831122 00002031700200001 BIB 5 9 2031700200002 REACTION (14-SI-28(N,P)13-AL-28,,SIG,,FIS) 2031700200003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031700200004 SAMPLE .SI-SQUARE PLATES 8 MILLIM. X 8 MILLIM. X 2031700200005 0.2 MILLIM, P-TYPE SINGLE CRYSTAL. 2031700200006 DECAY-DATA (13-AL-28,2.24MIN,DG) 2031700200007 HISTORY (711010C) 2031700200008 (740626E) 2031700200009 (800722A) REACTION RE-DEFINED. 2031700200010 (800808E) 2031700200011 ENDBIB 9 0 2031700200012 NOCOMMON 0 0 2031700200013 DATA 2 1 2031700200014 DATA DATA-ERR 2031700200015 MB MB 2031700200016 4.9000E+00 3.2000E-01 2031700200017 ENDDATA 3 0 2031700200018 ENDSUBENT 17 0 2031700299999 SUBENT 20317003 19831122 00002031700300001 BIB 5 9 2031700300002 REACTION (14-SI-29(N,P)13-AL-29,,SIG,,FIS) 2031700300003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031700300004 SAMPLE .SI-SQUARE PLATES 8 MILLIM. X 8 MILLIM. X 2031700300005 0.2 MILLIM, P-TYPE SINGLE CRYSTAL. 2031700300006 DECAY-DATA (13-AL-29,6.6MIN,DG) 2031700300007 HISTORY (711010C) 2031700300008 (740626E) 2031700300009 (800722A) REACTION RE-DEFINED. 2031700300010 (800808E) 2031700300011 ENDBIB 9 0 2031700300012 NOCOMMON 0 0 2031700300013 DATA 2 1 2031700300014 DATA DATA-ERR 2031700300015 MB MB 2031700300016 2.9800E+00 1.7000E-01 2031700300017 ENDDATA 3 0 2031700300018 ENDSUBENT 17 0 2031700399999 SUBENT 20317004 19831122 00002031700400001 BIB 5 9 2031700400002 REACTION (14-SI-30(N,A)12-MG-27,,SIG,,FIS) 2031700400003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031700400004 SAMPLE .SI-SQUARE PLATES 8 MILLIM. X 8 MILLIM. X 2031700400005 0.2 MILLIM, P-TYPE SINGLE CRYSTAL. 2031700400006 DECAY-DATA (12-MG-27,9.46MIN,DG) 2031700400007 HISTORY (711010C) 2031700400008 (740626E) 2031700400009 (800722A) REACTION RE-DEFINED. 2031700400010 (800808E) 2031700400011 ENDBIB 9 0 2031700400012 NOCOMMON 0 0 2031700400013 DATA 2 1 2031700400014 DATA DATA-ERR 2031700400015 MB MB 2031700400016 1.3000E-01 2.0000E-02 2031700400017 ENDDATA 3 0 2031700400018 ENDSUBENT 17 0 2031700499999 SUBENT 20317005 19831122 00002031700500001 BIB 6 10 2031700500002 REACTION (22-TI-46(N,P)21-SC-46-G,,SIG,,FIS) 2031700500003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031700500004 SAMPLE 99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM., 2031700500005 0.01 INCH THICK. 2031700500006 DECAY-DATA (21-SC-46-G,83.9D,DG,890.,,DG,1120.) 2031700500007 COMMENT 83.9 DAYS HL E ACTIVITY MEASURED. 2031700500008 HISTORY (711010C) 2031700500009 (740626E) 2031700500010 (800722A) REACTION RE-DEFINED. 2031700500011 (800808E) 2031700500012 ENDBIB 10 0 2031700500013 NOCOMMON 0 0 2031700500014 DATA 2 1 2031700500015 DATA DATA-ERR 2031700500016 MB MB 2031700500017 1.1200E+01 6.3000E-01 2031700500018 ENDDATA 3 0 2031700500019 ENDSUBENT 18 0 2031700599999 SUBENT 20317006 19831122 00002031700600001 BIB 6 12 2031700600002 REACTION (22-TI-46(N,P)21-SC-46-G,,SIG,,FIS) 2031700600003 INC-SOURCE (REAC ) NEUTRONS FROM ENRICHED U-235 PLATE PLACED 2031700600004 IN THE THERMAL NEUTRON IRRADIATION FACILITY 2031700600005 OF KUR-REACTOR. 2031700600006 SAMPLE 99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM., 2031700600007 0.01 INCH THICK. 2031700600008 DECAY-DATA (21-SC-46-G,83.9D,DG,890.,,DG,1120.) 2031700600009 COMMENT 83.9 DAYS HL E ACTIVITY MEASURED. 2031700600010 HISTORY (711010C) 2031700600011 (740626E) 2031700600012 (800721A) REACTION RE-DEFINED. 2031700600013 (800808E) 2031700600014 ENDBIB 12 0 2031700600015 NOCOMMON 0 0 2031700600016 DATA 2 1 2031700600017 DATA DATA-ERR 2031700600018 MB MB 2031700600019 1.0800E+01 6.1000E-01 2031700600020 ENDDATA 3 0 2031700600021 ENDSUBENT 20 0 2031700699999 SUBENT 20317007 19831122 00002031700700001 BIB 5 9 2031700700002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,FIS) 2031700700003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031700700004 SAMPLE 99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM., 2031700700005 0.01 INCH THICK. 2031700700006 DECAY-DATA (21-SC-47,3.42D,DG,160.) 2031700700007 HISTORY (711010C) 2031700700008 (740626E) 2031700700009 (800722A) REACTION RE-DEFINED. 2031700700010 (800808E) 2031700700011 ENDBIB 9 0 2031700700012 NOCOMMON 0 0 2031700700013 DATA 2 1 2031700700014 DATA DATA-ERR 2031700700015 MB MB 2031700700016 1.9000E+01 1.2000E+00 2031700700017 ENDDATA 3 0 2031700700018 ENDSUBENT 17 0 2031700799999 SUBENT 20317008 19831122 00002031700800001 BIB 5 11 2031700800002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,FIS) 2031700800003 INC-SOURCE (REAC ) NEUTRONS FROM ENRICHED U-235 PLATE PLACED 2031700800004 IN THE THERMAL NEUTRON IRRADIATION FACILITY 2031700800005 OF KUR-REACTOR. 2031700800006 SAMPLE 99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM., 2031700800007 0.01 INCH THICK. 2031700800008 DECAY-DATA (21-SC-47,3.42D,DG,160.) 2031700800009 HISTORY (711010C) 2031700800010 (740626E) 2031700800011 (800722A) REACTION RE-DEFINED. 2031700800012 (800808E) 2031700800013 ENDBIB 11 0 2031700800014 NOCOMMON 0 0 2031700800015 DATA 2 1 2031700800016 DATA DATA-ERR 2031700800017 MB MB 2031700800018 1.7300E+01 9.0000E-01 2031700800019 ENDDATA 3 0 2031700800020 ENDSUBENT 19 0 2031700899999 SUBENT 20317009 19831122 00002031700900001 BIB 5 9 2031700900002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,FIS) 2031700900003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031700900004 SAMPLE 99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM., 2031700900005 0.01 INCH THICK. 2031700900006 DECAY-DATA (21-SC-48,43.7HR,DG,980.,,DG,1040.,,DG,1314.) 2031700900007 HISTORY (711010C) 2031700900008 (740626E) 2031700900009 (800722A) REACTION RE-DEFINED. 2031700900010 (800808E) 2031700900011 ENDBIB 9 0 2031700900012 NOCOMMON 0 0 2031700900013 DATA 2 1 2031700900014 DATA DATA-ERR 2031700900015 MB MB 2031700900016 2.9400E-01 2.5000E-02 2031700900017 ENDDATA 3 0 2031700900018 ENDSUBENT 17 0 2031700999999 SUBENT 20317010 19831122 00002031701000001 BIB 5 11 2031701000002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,FIS) 2031701000003 INC-SOURCE (REAC ) NEUTRONS FROM ENRICHED U-235 PLATE PLACED 2031701000004 IN THE THERMAL NEUTRON IRRADIATION FACILITY 2031701000005 OF KUR-REACTOR. 2031701000006 SAMPLE 99.73 PERCENT PURE TI-FOILS, 0.5 INCH DIAM., 2031701000007 0.01 INCH THICK. 2031701000008 DECAY-DATA (21-SC-48,43.7HR,DG,980.,,DG,1040.,,DG,1314.) 2031701000009 HISTORY (711010C) 2031701000010 (740626E) 2031701000011 (800722A) REACTION RE-DEFINED. 2031701000012 (800808E) 2031701000013 ENDBIB 11 0 2031701000014 NOCOMMON 0 0 2031701000015 DATA 2 1 2031701000016 DATA DATA-ERR 2031701000017 MB MB 2031701000018 2.7200E-01 1.6000E-02 2031701000019 ENDDATA 3 0 2031701000020 ENDSUBENT 19 0 2031701099999 SUBENT 20317011 19831122 00002031701100001 BIB 5 9 2031701100002 REACTION (23-V-51(N,A)21-SC-48,,SIG,,FIS) 2031701100003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031701100004 SAMPLE 99.72 PERCENT PURE V-FOILS, 0.5 INCH DIAM., 2031701100005 0.003 INCH THICK. 2031701100006 DECAY-DATA (21-SC-48,43.7HR,DG,980.,,DG,1040.,,DG,1314.) 2031701100007 HISTORY (711010C) 2031701100008 (740626E) 2031701100009 (800722A) REACTION RE-DEFINED. 2031701100010 (800808E) 2031701100011 ENDBIB 9 0 2031701100012 NOCOMMON 0 0 2031701100013 DATA 2 1 2031701100014 DATA DATA-ERR 2031701100015 MB MB 2031701100016 2.1700E-02 1.5000E-03 2031701100017 ENDDATA 3 0 2031701100018 ENDSUBENT 17 0 2031701199999 SUBENT 20317012 19831122 00002031701200001 BIB 4 7 2031701200002 REACTION (30-ZN-64(N,P)29-CU-64,,SIG,,FIS) 2031701200003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031701200004 DECAY-DATA (29-CU-64,12.7HR,DG) 2031701200005 HISTORY (711010C) 2031701200006 (740626E) 2031701200007 (800722A) REACTION RE-DEFINED. 2031701200008 (800808E) 2031701200009 ENDBIB 7 0 2031701200010 NOCOMMON 0 0 2031701200011 DATA 2 1 2031701200012 DATA DATA-ERR 2031701200013 MB MB 2031701200014 3.5500E+01 2.8000E+00 2031701200015 ENDDATA 3 0 2031701200016 ENDSUBENT 15 0 2031701299999 SUBENT 20317013 19831122 00002031701300001 BIB 4 9 2031701300002 REACTION (30-ZN-64(N,P)29-CU-64,,SIG,,FIS) 2031701300003 INC-SOURCE (REAC ) NEUTRONS FROM ENRICHED U-235 PLATE PLACED 2031701300004 IN THE THERMAL NEUTRON IRRADIATION FACILITY 2031701300005 OF KUR-REACTOR. 2031701300006 DECAY-DATA (29-CU-64,12.7HR,DG) 2031701300007 HISTORY (711010C) 2031701300008 (740626E) 2031701300009 (800722A) REACTION RE-DEFINED. 2031701300010 (800808E) 2031701300011 ENDBIB 9 0 2031701300012 NOCOMMON 0 0 2031701300013 DATA 2 1 2031701300014 DATA DATA-ERR 2031701300015 MB MB 2031701300016 3.7400E+01 3.0000E+00 2031701300017 ENDDATA 3 0 2031701300018 ENDSUBENT 17 0 2031701399999 SUBENT 20317014 19831122 00002031701400001 BIB 6 10 2031701400002 REACTION (41-NB-93(N,2N)41-NB-92-M,,SIG,,FIS) 2031701400003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031701400004 SAMPLE 99.84 PERCENT PURE NB-FOILS, 0.5 INCH DIAM., 2031701400005 0.005 INCH THICK. 2031701400006 DECAY-DATA (41-NB-92-M,10.16D,DG) 2031701400007 COMMENT 10.16 DAYS HALF-LIFE ACTIVITY MEASURED. 2031701400008 HISTORY (711010C) 2031701400009 (740626E) 2031701400010 (800722A) REACTION RE-DEFINED. 2031701400011 (800808E) 2031701400012 ENDBIB 10 0 2031701400013 NOCOMMON 0 0 2031701400014 DATA 2 1 2031701400015 DATA DATA-ERR 2031701400016 MB MB 2031701400017 4.3200E-01 3.3000E-02 2031701400018 ENDDATA 3 0 2031701400019 ENDSUBENT 18 0 2031701499999 SUBENT 20317015 19831122 00002031701500001 BIB 6 12 2031701500002 REACTION (41-NB-93(N,2N)41-NB-92-M,,SIG,,FIS) 2031701500003 INC-SOURCE (REAC ) NEUTRONS FROM ENRICHED U-235 PLATE PLACED 2031701500004 IN THE THERMAL NEUTRON IRRADIATION FACILITY 2031701500005 OF KUR-REACTOR. 2031701500006 SAMPLE 99.84 PERCENT PURE NB-FOILS, 0.5 INCH DIAM., 2031701500007 0.005 INCH THICK. 2031701500008 DECAY-DATA (41-NB-92-M,10.16D,DG) 2031701500009 COMMENT 10.16 DAYS HALF-LIFE ACTIVITY MEASURED. 2031701500010 HISTORY (711010C) 2031701500011 (740626E) 2031701500012 (800722A) REACTION RE-DEFINED. 2031701500013 (800808E) 2031701500014 ENDBIB 12 0 2031701500015 NOCOMMON 0 0 2031701500016 DATA 2 1 2031701500017 DATA DATA-ERR 2031701500018 MB MB 2031701500019 4.0200E-01 3.4000E-02 2031701500020 ENDDATA 3 0 2031701500021 ENDSUBENT 20 0 2031701599999 SUBENT 20317016 19831122 00002031701600001 BIB 6 10 2031701600002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG,,FIS) 2031701600003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031701600004 SAMPLE 99.92 PERCENT PURE FOILS, 0.5 INCH DIAM., 2031701600005 0.003 INCH THICK. 2031701600006 DECAY-DATA (41-NB-92-M,10.16D,DG) 2031701600007 COMMENT 10.16 DAYS HALF-LIFE ACTIVITY MEASURED. 2031701600008 HISTORY (711010C) 2031701600009 (740626E) 2031701600010 (800722A) REACTION RE-DEFINED. 2031701600011 (800808E) 2031701600012 ENDBIB 10 0 2031701600013 NOCOMMON 0 0 2031701600014 DATA 2 1 2031701600015 DATA DATA-ERR 2031701600016 MB MB 2031701600017 6.0000E+00 4.3000E-01 2031701600018 ENDDATA 3 0 2031701600019 ENDSUBENT 18 0 2031701699999 SUBENT 20317017 19831122 00002031701700001 BIB 6 12 2031701700002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG,,FIS) 2031701700003 INC-SOURCE (REAC ) NEUTRONS FROM ENRICHED U-235 PLATE PLACED 2031701700004 IN THE THERMAL NEUTRON IRRADIATION FACILITY 2031701700005 OF KUR REACTOR. 2031701700006 SAMPLE 99.92 PERCENT PURE FOILS, 0.5 INCH DIAM., 2031701700007 0.003 INCH THICK. 2031701700008 DECAY-DATA (41-NB-92-M,10.16D,DG) 2031701700009 COMMENT 10.16 DAYS HALF-LIFE ACTIVITY MEASURED. 2031701700010 HISTORY (711010C) 2031701700011 (740626E) 2031701700012 (800722A) REACTION RE-DEFINED. 2031701700013 (800808E) 2031701700014 ENDBIB 12 0 2031701700015 NOCOMMON 0 0 2031701700016 DATA 2 1 2031701700017 DATA DATA-ERR 2031701700018 MB MB 2031701700019 6.0400E+00 4.5000E-01 2031701700020 ENDDATA 3 0 2031701700021 ENDSUBENT 20 0 2031701799999 SUBENT 20317018 19831122 00002031701800001 BIB 6 17 2031701800002 REACTION (82-PB-204(N,INL)82-PB-204-M,,SIG,,FIS) 2031701800003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031701800004 SAMPLE 99.99 PERCENT PURE FOILS, 10 MILLIM. X 2031701800005 10 MILLIM. X 1 MILLIM. 2031701800006 DECAY-DATA (82-PB-204-M,67.0MIN,DG,375.,,DG,899.,,DG,912.) 2031701800007 COMMENT .THE CROSS-SECTION OBTAINED FROM THE 375 KEV GAMMAS 2031701800008 WERE ABOUT 10 PERCENT LOWER THAN THOSE OBTAINED 2031701800009 FROM THE 899, 912 KEV GAMMAS. THIS DISCREPANCY MIGHT 2031701800010 BE DUE TO AN ERROR IN THE DECAY SCHEME TAKEN FROM 2031701800011 THE TABLE BY C.M.LEDERER ET AL., TABLE OF ISOTOPES, 2031701800012 6-TH ED., 1968. THE AVERAGE CROSS-SECTION VALUE IS 2031701800013 GIVEN. 2031701800014 67 MIN, HALF-LIFE ACTIVITY MEASURED. 2031701800015 HISTORY (711010C) 2031701800016 (740626E) 2031701800017 (800722A) REACTION RE-DEFINED. 2031701800018 (800808E) 2031701800019 ENDBIB 17 0 2031701800020 NOCOMMON 0 0 2031701800021 DATA 2 1 2031701800022 DATA DATA-ERR 2031701800023 MB MB 2031701800024 1.8900E+01 2.0000E+00 2031701800025 ENDDATA 3 0 2031701800026 ENDSUBENT 25 0 2031701899999 SUBENT 20317019 19831122 00002031701900001 BIB 6 10 2031701900002 REACTION (82-PB-204(N,2N)82-PB-203-G,,SIG,,FIS) 2031701900003 INC-SOURCE (REAC ) KUR-REACTOR, FISSION TYPE SPECTRUM. 2031701900004 SAMPLE 99.99 PERCENT PURE FOILS, 10 MILLIM. X 2031701900005 10 MILLIM. X 1 MILLIM. 2031701900006 DECAY-DATA (82-PB-203-G,52.1HR,DG) 2031701900007 COMMENT 52.1 HOURS HALF-LIFE ACTIVITY MEASURED. 2031701900008 HISTORY (711010C) 2031701900009 (740626E) 2031701900010 (800722A) REACTION RE-DEFINED. 2031701900011 (800808E) 2031701900012 ENDBIB 10 0 2031701900013 NOCOMMON 0 0 2031701900014 DATA 2 1 2031701900015 DATA DATA-ERR 2031701900016 MB MB 2031701900017 1.9000E+00 1.8000E-01 2031701900018 ENDDATA 3 0 2031701900019 ENDSUBENT 18 0 2031701999999 SUBENT 20317020 19831122 00002031702000001 BIB 5 6 2031702000002 REACTION (13-AL-27(N,P)12-MG-27,,SIG,,FIS) 2031702000003 INC-SOURCE (REAC ) FISSION PLATE IN KUR REACTOR. 2031702000004 SAMPLE .NO DETAILS. 2031702000005 STATUS .TABLE IN EUR-5667,142. 2031702000006 HISTORY (800723C) SUBWORK ADDED. 2031702000007 (800808E) 2031702000008 ENDBIB 6 0 2031702000009 NOCOMMON 0 0 2031702000010 DATA 2 1 2031702000011 DATA DATA-ERR 2031702000012 MB MB 2031702000013 3.4000E+00 1.0000E-01 2031702000014 ENDDATA 3 0 2031702000015 ENDSUBENT 14 0 2031702099999 ENDENTRY 20 0 2031799999999