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 SUPERSEDED. 2031700100007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 SUPERSEDED. 2031700100008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