ENTRY 21047 19810722 00002104700000001 SUBENT 21047001 19810722 00002104700100001 BIB 15 50 2104700100002 INSTITUTE (2SWTLAU) 2104700100003 REFERENCE (J,HPA,42,990,6906) 2104700100004 (W,G.A.GRIN,6607) NUMERICAL VALUES. 2104700100005 AUTHOR (G.A.GRIN,B.VAUCHER,J.C.ALDER,C.JOSEPH) 2104700100006 TITLE -C-12(N,N), (N,N') AND (N,N')3A REACTIONS AT 14 MEV- 2104700100007 FACILITY .NEUTRON GENERATOR OF THE INSTITUT DE PHYSIQUE 2104700100008 NUCLEAIRE DE L'UNIVERSITE DE LAUSANNE. 2104700100009 INC-SOURCE (D-T ) DEUTERON-TRITIUM, DEUTERON ENERGY 145 KEV. 2104700100010 SAMPLE .ONE DETECTOR ALSO SERVED AS SAMPLE. 2104700100011 METHOD (ASSOP) ORGANIC SCINTILLATOR SERVED AS SAMPLE AND 2104700100012 DETECTOR OF CARBON RECOILS AND ALPHAS. 2104700100013 NEUTRONS DETECTED AND THEIR TIME OF FLIGHT 2104700100014 MEASURED WITH RESPECT TO THESE ASSOCIATED 2104700100015 PARTICLES USING A SECOND SCINTILLATOR AND 2104700100016 FAST TOF SPECTROMETER. 2104700100017 (PHD ) ASSOCIATED CARBON RECOILS AND ALPHAS WERE 2104700100018 SEPARATED ON THE BASIS OF THEIR PULSE HEIGHT 2104700100019 AND USED TO FORM TWO NEUTRON TOF SPECTRA 2104700100020 SIMULTANEOUSLY BY MEANS OF A MULTIPLE FAST- 2104700100021 SLOW COINCIDENCE-ANTICOINCIDENCE SYSTEM AND 2104700100022 A 400 CHANNEL PHA (200 CHANNELS PER SPECTRUM). 2104700100023 DETECTOR (SCIN ) NE102A PLASTIC SCINTILLATOR, 10*10*3.8 CC, AS 2104700100024 NEUTRON DETECTOR COUPLED TO A 56AVP PHOTO- 2104700100025 MULTIPLIER. DETECTION THRESHOLD 500 KEV PROTON 2104700100026 ENERGY. DETECTOR SHIELDED FROM NEUTRON SOURCE 2104700100027 BY A 15 CM IRON SHADOW BAR. 2104700100028 NE102A SCINTILLATOR AS SCATTERER AND DETECTOR 2104700100029 OF ASSOCIATED PARTICLES PLACED 15 CM FROM THE 2104700100030 NEUTRON SOURCE. DIMENSIONS 1.8*2.4*2.8 CC FOR 2104700100031 THETA(LAB) LESS/EQUAL TO 30 DEG., 3.0*1.2*4.8 2104700100032 CC FOR THETA(LAB) GREATER THAN 30 DEG.. 2104700100033 MONITOR (1-H-1(N,EL)1-H-1,,SIG) SCATTERING BY HYDROGEN IN THE 2104700100034 SAMPLE SCINTILLATOR USED AS REFERENCE. CROSS- 2104700100035 SECTION GIVEN AS 690 MB AT 14.1 MEV. 2104700100036 PART-DET (N ) NEUTRONS 2104700100037 (A ) ALPHAS 2104700100038 (RCL ) CARBON RECOILS NUCLEI. 2104700100039 COMMENT .ANGULAR RESOLUTION 5 DEGREES (FWHM). 2104700100040 .TIME RESOLUTION 2 NANOSECONDS FOR ELASTICALLY 2104700100041 SCATTERED NEUTRONS. 2104700100042 .FLIGHT PATH 169 CM (0 TO 90 DEG.) AND 130 CM 2104700100043 (90 TO 150 DEG.). 2104700100044 STATUS (NDD ) FROM NEUDADA. NUMERICAL VALUES ORIGINALLY 2104700100045 FROM PRIVATE COMMUNICATION BY GRIN. 2104700100046 HISTORY (790808C) 2104700100047 (790831E) 2104700100048 (801118A) G.C., MONITOR REACTION STRING CORRECTED, 2104700100049 ERROR ANALYSIS INCLUDED. 2104700100050 (801218E) 2104700100051 ERR-ANALYS (ERR-T) TOTAL ERROR 2104700100052 ENDBIB 50 0 2104700100053 COMMON 3 3 2104700100054 EN EN-RSL MONIT 2104700100055 MEV MEV MB 2104700100056 1.4100E+01 5.0000E-02 6.9000E+02 2104700100057 ENDCOMMON 3 0 2104700100058 ENDSUBENT 57 0 2104700199999 SUBENT 21047002 19801218 00002104700200001 BIB 5 13 2104700200002 REACTION (6-C-12(N,EL)6-C-12,,DA) 2104700200003 ANALYSIS .VALUES DERIVED FROM THE MEASURED TOF SPECTRA. 2104700200004 STATUS (NDD ) FROM NEUDADA. GRAPHICAL DATA GIVEN IN THE 2104700200005 PUBLICATION, NUMERICAL VALUES FROM PRIVATE 2104700200006 COMMUNICATION OF GRIN. 2104700200007 HISTORY (790808C) 2104700200008 (790831E) 2104700200009 (801118A) G.C. DATA HEADINGS CHANGED 2104700200010 (801218E) 2104700200011 CORRECTION .CORRECTIONS APPLIED FOR RANDOM COINCIDENCES, BACK- 2104700200012 GROUND DUE TO PARASYTIC EVENTS, MULTIPLE SCATTERING 2104700200013 IN THE SAMPLE, ABSORPTION OF INCOMING AND SCATTERED 2104700200014 NEUTRONS IN THE SAMPLE, ABSORPTION IN AIR. 2104700200015 ENDBIB 13 0 2104700200016 NOCOMMON 0 0 2104700200017 DATA 3 8 2104700200018 COS-CM DATA ERR-T 2104700200019 NO-DIM MB/SR MB/SR 2104700200020 -8.8620E-01 2.0000E+01 1.1000E+00 2104700200021 -7.4780E-01 1.9000E+01 1.2000E+00 2104700200022 -5.6210E-01 2.9800E+01 8.0000E-01 2104700200023 -3.3710E-01 3.6000E+01 2.0000E+00 2104700200024 -8.3700E-02 3.4000E+01 1.0000E+00 2104700200025 1.7880E-01 2.1000E+01 1.8000E+00 2104700200026 4.3520E-01 1.8500E+01 1.0000E+00 2104700200027 6.6390E-01 5.6000E+01 2.5000E+00 2104700200028 ENDDATA 10 0 2104700200029 ENDSUBENT 28 0 2104700299999 SUBENT 21047003 19810722 00002104700300001 BIB 4 7 2104700300002 REACTION (6-C-12(N,EL)6-C-12,,SIG) 2104700300003 ANALYSIS (INTAD) INTEGRATION OF ANGULAR DISTRIBUTION. 2104700300004 STATUS (DEP,21047002) FROM MEASURED ANGULAR DISTRIBUTION. 2104700300005 HISTORY (790808C) 2104700300006 (790831E) 2104700300007 (801118A) G.C., DATA HEADINGS CHANGED. 2104700300008 (801218E) 2104700300009 ENDBIB 7 0 2104700300010 NOCOMMON 0 0 2104700300011 DATA 2 1 2104700300012 DATA ERR-T 2104700300013 MB MB 2104700300014 7.7500E+02 3.5000E+01 2104700300015 ENDDATA 3 0 2104700300016 ENDSUBENT 15 0 2104700399999 SUBENT 21047004 19810722 00002104700400001 BIB 5 13 2104700400002 REACTION (6-C-12(N,INL)6-C-12,PAR,DA) 2104700400003 ANALYSIS .VALUES DERIVED FROM THE MEASURED TOF SPECTRA. 2104700400004 STATUS (NDD ) FROM NEUDADA. GRAPHICAL DATA GIVEN IN THE 2104700400005 PUBLICATION, NUMERICAL VALUES FROM PRIVATE 2104700400006 COMMUNICATION OF GRIN. 2104700400007 HISTORY (790808C) 2104700400008 (790831E) 2104700400009 (801118A) G.C., DATA HEADINGS CHANGED 2104700400010 (801218E) 2104700400011 CORRECTION .CORRECTIONS APPLIED FOR RANDOM COINCIDENCES, BACK- 2104700400012 GROUND DUE TO PARASYTIC EVENTS, MULTIPLE SCATTERING 2104700400013 IN THE SAMPLE, ABSORPTION OF INCOMING AND SCATTERED 2104700400014 NEUTRONS IN THE SAMPLE, ABSORPTION IN AIR. 2104700400015 ENDBIB 13 0 2104700400016 NOCOMMON 0 0 2104700400017 DATA 5 56 2104700400018 Q-VAL COS-CM DATA ERR-T DATA-MAX 2104700400019 MEV NO-DIM MB/SR MB/SR MB/SR 2104700400020 -1.1820E+01-6.9340E-01 4.0000E-01 2104700400021 -1.1820E+01-5.0900E-01 4.0000E-01 2104700400022 -1.1820E+01-2.7900E-01 4.0000E-01 2104700400023 -1.1820E+01 2.7730E-01 4.0000E-01 2104700400024 -1.1820E+01 5.5480E-01 5.0000E-01 2.0000E-01 2104700400025 -1.1820E+01 7.8800E-01 6.0000E-01 2.0000E-01 2104700400026 -1.1820E+01 8.7880E-01 1.2000E+00 6.0000E-01 2104700400027 -1.1820E+01 9.4490E-01 5.5000E-01 2.0000E-01 2104700400028 -1.1820E+01 9.8330E-01 6.5000E-01 4.0000E-01 2104700400029 -1.1820E+01 9.9780E-01 6.0000E-01 2.5000E-01 2104700400030 -1.0840E+01-9.1280E-01 3.1000E+00 4.5000E-01 2104700400031 -1.0840E+01-8.0280E-01 1.6000E+00 2.5000E-01 2104700400032 -1.0840E+01-6.4680E-01 1.4500E+00 2.5000E-01 2104700400033 -1.0840E+01-4.4620E-01 1.3000E+00 3.0000E-01 2104700400034 -1.0840E+01-2.0620E-01 8.0000E-01 1.5000E-01 2104700400035 -1.0840E+01 6.1000E-02 6.0000E-01 2.5000E-01 2104700400036 -1.0840E+01 3.3710E-01 5.0000E-01 2.0000E-01 2104700400037 -1.0840E+01 5.9620E-01 9.5000E-01 3.0000E-01 2104700400038 -1.0840E+01 8.1000E-01 1.0000E+00 2.0000E-01 2104700400039 -1.0840E+01 8.9100E-01 8.0000E-01 5.0000E-01 2104700400040 -1.0840E+01 9.5110E-01 6.5000E-01 2.0000E-01 2104700400041 -1.0840E+01 9.8420E-01 6.5000E-01 2.5000E-01 2104700400042 -1.0840E+01 9.9800E-01 9.0000E-01 2.5000E-01 2104700400043 -9.6300E+00-9.0410E-01 1.4000E+00 2.0000E-01 2104700400044 -9.6300E+00-7.8480E-01 2.2000E+00 3.0000E-01 2104700400045 -9.6300E+00-6.1840E-01 3.6500E+00 2.5000E-01 2104700400046 -9.6300E+00-4.0990E-01 4.6500E+00 4.0000E-01 2104700400047 -9.6300E+00-1.6500E-01 4.7000E+00 2.0000E-01 2104700400048 -9.6300E+00 1.0110E-01 5.5000E+00 5.5000E-01 2104700400049 -9.6300E+00 3.7140E-01 6.3000E+00 4.0000E-01 2104700400050 -9.6300E+00 6.1980E-01 6.7000E+00 4.0000E-01 2104700400051 -9.6300E+00 8.2210E-01 6.8500E+00 3.5000E-01 2104700400052 -9.6300E+00 8.9880E-01 7.4500E+00 8.5000E-01 2104700400053 -9.6300E+00 9.5370E-01 7.1500E+00 5.0000E-01 2104700400054 -9.6300E+00 9.8770E-01 7.3000E+00 6.5000E-01 2104700400055 -9.6300E+00 9.9810E-01 8.2000E+00 6.5000E-01 2104700400056 -7.6600E+00-8.9730E-01 1.1000E+00 2.5000E-01 2104700400057 -7.6600E+00-7.6940E-01 6.5000E-01 2.0000E-01 2104700400058 -7.6600E+00-5.9480E-01 2.0000E-01 1.0000E-01 2104700400059 -7.6600E+00-3.7950E-01 3.0000E-01 1.5000E-01 2104700400060 -7.6600E+00-1.3050E-01 4.0000E-01 1.0000E-01 2104700400061 -7.6600E+00 1.3400E-01 5.5000E-01 2.5000E-01 2104700400062 -7.6600E+00 3.9870E-01 4.5000E-01 1.5000E-01 2104700400063 -7.6600E+00 8.3100E-01 1.1500E+00 2.0000E-01 2104700400064 -7.6600E+00 9.0560E-01 2.3500E+00 6.0000E-01 2104700400065 -7.6600E+00 9.5630E-01 3.4500E+00 4.5000E-01 2104700400066 -7.6600E+00 9.8770E-01 4.1000E+00 6.5000E-01 2104700400067 -7.6600E+00 9.9810E-01 4.3000E+00 6.5000E-01 2104700400068 -4.4300E+00-8.8540E-01 2.2200E+01 1.2000E+00 2104700400069 -4.4300E+00-7.5700E-01 1.6200E+01 1.0000E+00 2104700400070 -4.4300E+00-5.7500E-01 1.1600E+01 8.0000E-01 2104700400071 -4.4300E+00-3.5350E-01 1.0600E+01 1.0000E+00 2104700400072 -4.4300E+00-1.0280E-01 7.8000E+00 5.0000E-01 2104700400073 -4.4300E+00 1.6160E-01 8.6000E+00 1.0000E+00 2104700400074 -4.4300E+00 4.2100E-01 1.2900E+01 8.0000E-01 2104700400075 -4.4300E+00 6.5340E-01 2.0500E+01 1.5000E+00 2104700400076 ENDDATA 58 0 2104700400077 ENDSUBENT 76 0 2104700499999 SUBENT 21047005 19810722 00002104700500001 BIB 4 12 2104700500002 REACTION (6-C-12(N,INL)6-C-12,PAR,DA) 2104700500003 .CROSS-SECTION IN TWO ENERGY RANGES TO THE NEUTRON 2104700500004 CONTINUUM UNDERLYING NEUTRONS FROM TRANSITIONS TO 2104700500005 THE LEVELS AT 9.63, 10.84 AND 11.82 MEV. 2104700500006 ANALYSIS .VALUES DERIVED FROM MEASURED TOF SPECTRA. 2104700500007 STATUS (NDD ) FROM NEUDADA. GRAPHICAL DATA GIVEN IN THE 2104700500008 PUBLICATION, NUMERICAL VALUES FROM PRIVATE 2104700500009 COMMUNICATION BY GRIN. 2104700500010 HISTORY (790808C) 2104700500011 (790831E) 2104700500012 (801118A) G.C., DATA HEADINGS CHANGED. 2104700500013 (801218E) 2104700500014 ENDBIB 12 0 2104700500015 NOCOMMON 0 0 2104700500016 DATA 5 26 2104700500017 E-MIN E-MAX COS-CM DATA ERR-T 2104700500018 MEV MEV NO-DIM MB/SR MB/SR 2104700500019 0.0000E+00 2.3000E+00-9.0700E-01 7.7500E+00 2.9000E+00 2104700500020 0.0000E+00 2.3000E+00-7.9020E-01 6.7500E+00 1.9000E+00 2104700500021 0.0000E+00 2.3000E+00-6.2730E-01 6.4000E+00 1.3500E+00 2104700500022 0.0000E+00 2.3000E+00-4.2100E-01 8.0000E+00 1.9000E+00 2104700500023 0.0000E+00 2.3000E+00-1.7710E-01 7.3000E+00 9.0000E-01 2104700500024 0.0000E+00 2.3000E+00 8.8900E-02 9.0000E+00 2.4000E+00 2104700500025 0.0000E+00 2.3000E+00 3.6080E-01 8.0000E+00 2.6000E+00 2104700500026 0.0000E+00 2.3000E+00 6.1290E-01 8.4500E+00 1.9500E+00 2104700500027 0.0000E+00 2.3000E+00 8.1820E-01 6.1000E+00 1.1000E+00 2104700500028 0.0000E+00 2.3000E+00 8.9490E-01 5.9000E+00 3.4000E+00 2104700500029 0.0000E+00 2.3000E+00 9.5270E-01 6.5000E+00 1.6000E+00 2104700500030 0.0000E+00 2.3000E+00 9.8480E-01 6.3000E+00 2.4000E+00 2104700500031 0.0000E+00 2.3000E+00 9.9810E-01 6.0000E+00 2.3000E+00 2104700500032 1.0000E+00 1.3100E+01-9.0700E-01 5.6000E+00 2.1000E+00 2104700500033 1.0000E+00 1.3100E+01-7.9020E-01 5.2500E+00 1.4500E+00 2104700500034 1.0000E+00 1.3100E+01-6.2730E-01 5.2000E+00 1.1000E+00 2104700500035 1.0000E+00 1.3100E+01-4.2100E-01 7.1500E+00 1.7000E+00 2104700500036 1.0000E+00 1.3100E+01-1.7710E-01 7.3000E+00 9.0000E-01 2104700500037 1.0000E+00 1.3100E+01 8.8900E-02 9.9000E+00 2.7000E+00 2104700500038 1.0000E+00 1.3100E+01 3.6080E-01 9.6000E+00 3.2000E+00 2104700500039 1.0000E+00 1.3100E+01 6.1290E-01 1.1500E+01 2.6500E+00 2104700500040 1.0000E+00 1.3100E+01 8.1820E-01 8.6000E+00 1.5500E+00 2104700500041 1.0000E+00 1.3100E+01 8.9490E-01 8.3000E+00 4.8000E+00 2104700500042 1.0000E+00 1.3100E+01 9.5270E-01 9.2000E+00 2.3000E+00 2104700500043 1.0000E+00 1.3100E+01 9.8480E-01 8.8500E+00 3.4000E+00 2104700500044 1.0000E+00 1.3100E+01 9.9810E-01 8.4000E+00 3.2000E+00 2104700500045 ENDDATA 28 0 2104700500046 ENDSUBENT 45 0 2104700599999 SUBENT 21047006 19800228 00002104700600001 BIB 3 7 2104700600002 REACTION (6-C-12(N,INL)6-C-12,PAR,SIG) 2104700600003 .INTEGRATED CROSS-SECTIONS FOR TRANSITIONS TO NEUTRON 2104700600004 CONTINUUM IN TW0 ENERGY RANGES. 2104700600005 ANALYSIS (INTAD) INTEGRATION OF MEASURED ANGULAR DISTRIBUTION. 2104700600006 STATUS (DEP ) FROM MEASURED ANGULAR DISTRIBUTION. 2104700600007 (NDD ) FROM NEUDADA. NUMERICAL VALUES ARE ALSO GIVEN 2104700600008 IN THE PUBLICATION. 2104700600009 ENDBIB 7 0 2104700600010 NOCOMMON 0 0 2104700600011 DATA 3 2 2104700600012 E-MIN E-MAX DATA 2104700600013 MEV MEV MB 2104700600014 0.0000E+00 2.3000E+00 9.4000E+01 2104700600015 1.0000E+00 1.3100E+01 1.0200E+02 2104700600016 ENDDATA 4 0 2104700600017 ENDSUBENT 16 0 2104700699999 SUBENT 21047007 19810722 00002104700700001 BIB 3 11 2104700700002 REACTION (6-C-12(N,INL)6-C-12,PAR,DA) 2104700700003 .MAXIMUM POSSIBLE CONTRIBUTION OF THE 10.1 MEV LEVEL, 2104700700004 OF WIDTH 2.5 MEV, TO THE NEUTRON CONTINUUM. 2104700700005 STATUS (DEP ) DATA DEPENDS ON MEASURED NEUTRON CONTINUUM. 2104700700006 (NDD ) FROM NEUDADA. GRAPHICAL DATA GIVEN IN THE 2104700700007 PUBLICATION, NUMERICAL VALUES FROM PRIVATE 2104700700008 COMMUNICATION OF GRIN. 2104700700009 HISTORY (790808C) 2104700700010 (790831E) 2104700700011 (801118A) G.C., DATA HEADINGS CHANGED. 2104700700012 (801218E) 2104700700013 ENDBIB 11 0 2104700700014 COMMON 2 3 2104700700015 Q-VAL E-RSL 2104700700016 MEV MEV 2104700700017 -1.0100E+01 3.0000E+00 2104700700018 ENDCOMMON 3 0 2104700700019 DATA 3 13 2104700700020 COS-CM DATA ERR-T 2104700700021 NO-DIM MB/SR MB/SR 2104700700022 -9.0700E-01 4.1000E+00 1.6000E+00 2104700700023 -7.9020E-01 3.3000E+00 1.1000E+00 2104700700024 -6.2730E-01 3.0000E+00 8.0000E-01 2104700700025 -4.2100E-01 4.0000E+00 1.1000E+00 2104700700026 -1.7710E-01 4.6000E+00 8.0000E-01 2104700700027 8.8900E-02 5.7000E+00 1.6000E+00 2104700700028 3.6080E-01 5.3000E+00 1.6000E+00 2104700700029 6.1290E-01 5.2000E+00 1.4000E+00 2104700700030 8.1820E-01 4.0000E+00 8.0000E-01 2104700700031 8.9490E-01 3.9000E+00 2.2000E+00 2104700700032 9.5270E-01 4.2000E+00 1.1000E+00 2104700700033 9.8480E-01 4.2000E+00 1.7000E+00 2104700700034 9.9810E-01 4.0000E+00 1.8000E+00 2104700700035 ENDDATA 15 0 2104700700036 ENDSUBENT 35 0 2104700799999 SUBENT 21047008 19810722 00002104700800001 BIB 4 15 2104700800002 REACTION (6-C-12(N,INL)6-C-12,PAR,DA) 2104700800003 .CROSS-SECTION TO NEUTRON CONTINUUM AFTER MAXIMUM 2104700800004 POSSIBLE CONTRIBUTION FROM 10.1 MEV STATE HAS BEEN 2104700800005 SUBTRACTED. 2104700800006 ANALYSIS (INTAD) INTEGRATION OF MEASURED ANGULAR DISTRIBUTION. 2104700800007 STATUS (DEP ) FROM MEASURED CONTINUUM CROSS-SECTION AND 2104700800008 ESTIMATED MAXIMUM CONTRIBUTION FROM 10.1 MEV 2104700800009 LEVEL. 2104700800010 (NDD ) FROM NEUDADA. GRAPHICAL DATA GIVEN IN THE 2104700800011 PUBLICATION, NUMERICAL VALUES FROM PRIVATE 2104700800012 COMMUNICATION OF GRIN. 2104700800013 HISTORY (790808C) 2104700800014 (790831E) 2104700800015 (801118A) G.C., DATA HEADINGS CHANGED. 2104700800016 (801218E) 2104700800017 ENDBIB 15 0 2104700800018 COMMON 1 3 2104700800019 E-MIN 2104700800020 MEV 2104700800021 1.0000E+00 2104700800022 ENDCOMMON 3 0 2104700800023 DATA 3 13 2104700800024 COS-CM DATA ERR-T 2104700800025 NO-DIM MB/SR MB/SR 2104700800026 -9.0700E-01 2.3000E+00 1.2000E+00 2104700800027 -7.9020E-01 2.6000E+00 1.0000E+00 2104700800028 -6.2730E-01 2.6000E+00 8.0000E-01 2104700800029 -4.2100E-01 3.6000E+00 1.0000E+00 2104700800030 -1.7710E-01 3.1000E+00 5.0000E-01 2104700800031 8.8900E-02 5.4000E+00 1.3000E+00 2104700800032 3.6080E-01 4.2000E+00 1.2000E+00 2104700800033 6.1290E-01 6.0000E+00 1.1000E+00 2104700800034 8.1820E-01 4.2000E+00 6.0000E-01 2104700800035 8.9490E-01 4.3000E+00 1.6000E+00 2104700800036 9.5270E-01 4.6000E+00 8.0000E-01 2104700800037 9.8480E-01 4.4000E+00 1.4000E+00 2104700800038 9.9810E-01 4.0000E+00 1.4000E+00 2104700800039 ENDDATA 15 0 2104700800040 ENDSUBENT 39 0 2104700899999 SUBENT 21047009 19810722 00002104700900001 BIB 3 12 2104700900002 REACTION (6-C-12(N,INL)6-C-12,PAR,SIG) 2104700900003 .CROSS-SECTION TO NEUTRON CONTINUUM AFTER MAXIMUM 2104700900004 POSSIBLE CONTRIBUTION FROM 10.1 MEV STATE HAS BEEN 2104700900005 SUBTRACTED. 2104700900006 STATUS (DEP,21047008) FROM MEASURED CONTINUUM CROSS-SECTION 2104700900007 AND ESTIMATED MAXIMUM CONTRIBUTION FROM 10.1 M 2104700900008 MEV LEVEL. 2104700900009 (NDD ) FROM NEUDADA. DATA ALSO IN PUBLICATION. 2104700900010 HISTORY (790808C) 2104700900011 (790831E) 2104700900012 (801118A) G.C., DATA HEADINGS CHANGED. 2104700900013 (801218E) 2104700900014 ENDBIB 12 0 2104700900015 NOCOMMON 0 0 2104700900016 DATA 3 1 2104700900017 E-MIN DATA ERR-T 2104700900018 MEV MB MB 2104700900019 1.0000E+00 4.5000E+01 1.0000E+01 2104700900020 ENDDATA 3 0 2104700900021 ENDSUBENT 20 0 2104700999999 SUBENT 21047010 19810722 00002104701000001 BIB 4 8 2104701000002 REACTION (6-C-12(N,INL)6-C-12,PAR,SIG) 2104701000003 ANALYSIS (INTAD) INTEGRATION OF MEASURED ANGULAR DISTRIBUTION. 2104701000004 STATUS (DEP,21047004) FROM MEASURED ANGULAR DISTRIBUTION. 2104701000005 (NDD ) FROM NEUDADA. DATA IN TABLE 1 OF PUBLICATION. 2104701000006 HISTORY (790808C) 2104701000007 (790831E) 2104701000008 (801118A) G.C., DATA HEADINGS CHANGED. 2104701000009 (801218E) 2104701000010 ENDBIB 8 0 2104701000011 NOCOMMON 0 0 2104701000012 DATA 3 6 2104701000013 Q-VAL DATA ERR-T 2104701000014 MEV MB MB 2104701000015 -1.1820E+01 3.5000E+00 3.0000E+00 2104701000016 -1.0840E+01 1.3500E+01 3.0000E+00 2104701000017 -1.0100E+01 5.5000E+01 1.2000E+01 2104701000018 -9.6300E+00 6.2500E+01 5.0000E+00 2104701000019 -7.6600E+00 8.5000E+00 2.0000E+00 2104701000020 -4.4300E+00 2.1500E+02 1.5000E+01 2104701000021 ENDDATA 8 0 2104701000022 ENDSUBENT 21 0 2104701099999 SUBENT 21047011 19810722 00002104701100001 BIB 4 10 2104701100002 REACTION (6-C-12(N,N+2A)2-HE-4,PAR,SIG) 2104701100003 .CROSS-SECTION FOR N,N+3A BEGINNING WITH THE EMISSION 2104701100004 OF AN INELASTIC NEUTRON. 2104701100005 EN-SEC (E-LVL-MIN,6-C-12) 2104701100006 (E-LVL-MAX,6-C-12) 2104701100007 STATUS (NDD ) FROM NEUDADA AND TABLE 1 OF PUBLICATION. 2104701100008 HISTORY (790808C) 2104701100009 (790831E) 2104701100010 (801118A) G.C., DATA HEADINGS CHANGED. 2104701100011 (801218E) 2104701100012 ENDBIB 10 0 2104701100013 NOCOMMON 0 0 2104701100014 DATA 4 1 2104701100015 E-LVL-MIN E-LVL-MAX DATA ERR-T 2104701100016 MEV MEV MB MB 2104701100017 7.6600E+00 1.1820E+01 1.1500E+02 4.0000E+01 2104701100018 ENDDATA 3 0 2104701100019 ENDSUBENT 18 0 2104701199999 SUBENT 21047012 19801218 00002104701200001 BIB 3 11 2104701200002 REACTION (6-C-12(N,N+2A)2-HE-4,,SIG) 2104701200003 .CROSS-SECTION FOR ALL PROCESSES LEADING TO A NEUTRON 2104701200004 AND 3 ALPHAS, I.E. INITIAL INELASTIC EMISSION PLUS 2104701200005 MAXIMUM CONTRIBUTION OF DIRECT BREAKUP FROM 4-BODY 2104701200006 PHASE SPACE FIT TO THE CONTINUUM. 2104701200007 STATUS (NDD ) FROM NEUDADA. DATA GIVEN IN TABLE 1 OF THE 2104701200008 PUBLICATION. 2104701200009 HISTORY (790808C) 2104701200010 (790831E) 2104701200011 (801118A) G.C., DATA HEADINGS CHANGED. 2104701200012 (801218E) 2104701200013 ENDBIB 11 0 2104701200014 NOCOMMON 0 0 2104701200015 DATA 2 1 2104701200016 DATA ERR-T 2104701200017 MB MB 2104701200018 1.9000E+02 2.0000E+01 2104701200019 ENDDATA 3 0 2104701200020 ENDSUBENT 19 0 2104701299999 ENDENTRY 12 0 2104799999999