ENTRY 40064 20201010 41934006400000001 SUBENT 40064001 20201010 41934006400100001 BIB 10 58 4006400100002 INSTITUTE (4RUSNIR) 4006400100003 REFERENCE (J,AE,29,95,1970) Issue 2. Data of NU-BAR and only 4006400100004 graphs of spectra are given. 4006400100005 (J,SJA,29,790,1970) Engl. translation of J,AE 4006400100006 #doi:10.1007/BF01159590 4006400100007 (C,70HELSINKI,2,183,1970) IAEA-CN-26/90 4006400100008 =STI/PUB-259,(2),183,1970 4006400100009 First author Ju.S.Zamyatnin. 4006400100010 Presented by S.L.Sukhoruchkin. 4006400100011 AUTHOR (N.I.Kroshkin,Yu.S.Zamyatnin,A.K.Mel'nikov,V.N.Nefedov)4006400100012 TITLE Measurement of energy spectrum and average number 4006400100013 of prompt fission neutrons 4006400100014 METHOD (TOF) Time-of-flight method for measurement of prompt4006400100015 neutron spectra used . TOF base 50 cm. Time resolution 4006400100016 3.5 nsec. 4006400100017 (COINC) Coincidence 4006400100018 Neutron spectra of investigated isotopes were measured 4006400100019 intermittently with measurement of U235 fission neutron4006400100020 spectrum by thermal neutrons. U-235 spectrum was 4006400100021 supposed to be proportional to sqrt(E)*exp(-E/T) with 4006400100022 T=1.29 MeV. Parameters of U-235 spectrum: 4006400100023 ASSUMED (ASSUM1,92-U-235(N,F)0-NN-1,,KEM) 4006400100024 (ASSUM2,92-U-235(N,F)0-NN-1,PR,KE) 4006400100025 Average kinetic energy of prompt 4006400100026 fission neutrons at fission by thermal neutrons . 4006400100027 NU is given in Subents 002-007 as MONIT. 4006400100028 DETECTOR (SCIN) Scintillation detectors: 4006400100029 -Gas scintillation chamber - for fission fragments 4006400100030 registration. 40 cm diameter, 40 cm long, filled with 4006400100031 helium, connected with FEU-53. 4006400100032 -Plastic scintillator - for neutrons registration . 4006400100033 100 mm diameter, 30 mm long, connected with FEU-63, 4006400100034 Protected by 15 mm lead layer. Detector threshold was 4006400100035 constantly controls by 59.6 keV gammas of Am-241. 4006400100036 Neutron detector efficiency dependence from energy was 4006400100037 determined by U-235 neutron spectrum, taking into 4006400100038 account T=1.29 MeV. 4006400100039 PART-DET (FF) 4006400100040 (N) 4006400100041 CORRECTION Background of random coincidence was taken into account4006400100042 HISTORY (19730925C) Compiled at the centre 4006400100043 (19750210A) ISO-QUANT in SUBENTS 007 and 013 corrected 4006400100044 (20120302A) Upper -> lover case correction. 4006400100045 Dates were corrected for 4-digits year. 4006400100046 Units were corrected NO-DIM -> PRT/FIS for NU. AKE->KE.4006400100047 BIB and COMMON information was added. 4006400100048 Subents 14-20 were added. 4006400100049 (20140709A) Ref. 70HELSINKI,,183,1970 was added. 4006400100050 Subents 021-030 were added. 4006400100051 BIB information was updated. 4006400100052 Authors' names from 70HELSINKI were added. 4006400100053 (20160512A) SD: SF1=Am-242m1 -> Am-242m in REACTION 4006400100054 codes of Subents 002, 008, 015, 024. 4006400100055 (See: Phys.Ref.,166,1219,1968, (Entry 12572) whereas 4006400100056 second ref. in NSE,32,131,1968 that used in this publ.)4006400100057 (20170710U) M.M. Previous correction of SD was 4006400100058 checked at CJD . 4006400100059 (20201010A) Subents 003,004 were corrected. 4006400100060 ENDBIB 58 0 4006400100061 COMMON 2 3 4006400100062 ASSUM1 ASSUM2 4006400100063 MEV MEV 4006400100064 1.29 1.935 4006400100065 ENDCOMMON 3 0 4006400100066 ENDSUBENT 65 0 4006400199999 SUBENT 40064002 20160512 41764006400200001 BIB 10 19 4006400200002 REACTION (95-AM-242-M(N,F),PR,NU) 4006400200003 INC-SOURCE (REAC) Reactor SM-2. 4006400200004 INC-SPECT Measurements were done with and without Cd. 4006400200005 Cadmium ratio 20. 4006400200006 FACILITY (REAC,4RUSNIR) SM-2 reactor. 4006400200007 SAMPLE Am-241 - 88.97%, Am-242 - 1.03%, Am-243 - 10.00%. 4006400200008 30 microg. 4006400200009 MONITOR (92-U-235(N,F),PR,NU) 4006400200010 Prompt NU-BAR at fission by 4006400200011 thermal neutrons. 4006400200012 ANALYSIS Measured neutron spectrum was integrated. 4006400200013 ERR-ANALYS (DATA-ERR) Error of relative measurements was equal 4006400200014 to about 3% 4006400200015 Error of absolute NU-BAR is average-squared on five 4006400200016 series of measurements . 4006400200017 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006400200018 The same data in Table 3 of C,70HELSINKI . 4006400200019 (DEP,40064027) Measured spectrum. 4006400200020 HISTORY (20160512A) SD:SF4=Am-242m1 -> Am-242m in REACTION code4006400200021 ENDBIB 19 0 4006400200022 COMMON 2 3 4006400200023 EN MONIT 4006400200024 EV PRT/FIS 4006400200025 2.5300E-02 2.4260E+00 4006400200026 ENDCOMMON 3 0 4006400200027 DATA 2 1 4006400200028 DATA DATA-ERR 4006400200029 PRT/FIS PRT/FIS 4006400200030 3.2800E+00 1.0000E-01 4006400200031 ENDDATA 3 0 4006400200032 ENDSUBENT 31 0 4006400299999 SUBENT 40064003 20201010 41934006400300001 BIB 7 19 4006400300002 REACTION (96-CM-244(0,F),PR,NU) 4006400300003 SAMPLE 20 microg. Produced by Pu-242 activation in SM-2 4006400300004 reactor. Am-243 and Pu-238 admixtures < 0.3% each. 4006400300005 Cm-244 - 96.38%, Cm-242 - 0.05%, 4006400300006 Cm-243 < 0.35%, Cm-245 - 1.75%, Cm-246 - 1.47%. 4006400300007 MONITOR (92-U-235(N,F),PR,NU) 4006400300008 Prompt NU-BAR at fission by 4006400300009 thermal neutrons 4006400300010 ANALYSIS Measured neutron spectrum was integrated. 4006400300011 ERR-ANALYS (DATA-ERR) Error of relative measurements was 4006400300012 equal to about 3 percent. 4006400300013 Error of absolute NU-BAR is average-squared on five 4006400300014 series of measurements 4006400300015 STATUS (TABLE) Table 2 of Atom.Energiya,v.29,is.2,p.95,1970. 4006400300016 The same data in Table 3 of C,70HELSINKI . 4006400300017 (DEP,40064025) Measured spectrum. 4006400300018 (SPSDD,40297008) In 40297007 data normalized to 4006400300019 NU=2.407 prt/fis for U-235 monitor in newer publication4006400300020 HISTORY (20201010A) Code SPSDD was added in Status 4006400300021 ENDBIB 19 0 4006400300022 COMMON 2 3 4006400300023 MONIT EN-NRM 4006400300024 PRT/FIS EV 4006400300025 2.4260E+00 0.0235 4006400300026 ENDCOMMON 3 0 4006400300027 DATA 2 1 4006400300028 DATA DATA-ERR 4006400300029 PRT/FIS PRT/FIS 4006400300030 2.7700E+00 8.0000E-02 4006400300031 ENDDATA 3 0 4006400300032 ENDSUBENT 31 0 4006400399999 SUBENT 40064004 20201010 41934006400400001 BIB 9 17 4006400400002 REACTION (96-CM-245(N,F),PR,NU) 4006400400003 INC-SOURCE (REAC) Reactor SM-2. 4006400400004 FACILITY (REAC,4RUSNIR) SM-2 reactor. 4006400400005 INC-SPECT Measurements were done with and without Cd. 4006400400006 MONITOR (92-U-235(N,F),PR,NU) 4006400400007 Prompt NU-BAR at fission by thermal neutrons 4006400400008 ANALYSIS Measured neutron spectrum was integrated. 4006400400009 ERR-ANALYS (DATA-ERR) Error of relative measurements was 4006400400010 equal to about 3 percent. 4006400400011 Error of absolute NU-BAR is average-squared on five 4006400400012 series of measurements. 4006400400013 STATUS (TABLE) Table 2 of Atom.Energiya,v.29,is.2,p.95,1970 4006400400014 The same data in Table 3 of C,70HELSINKI . 4006400400015 (DEP,40064025) Measured spectrum. 4006400400016 (SPSDD,40297011) In 40297011 data normalized to 4006400400017 NU=2.407 prt/fis for U-235 monitor in newer publication4006400400018 HISTORY (20201010A) Free text was corrected in Status 4006400400019 ENDBIB 17 0 4006400400020 COMMON 2 3 4006400400021 EN MONIT 4006400400022 EV PRT/FIS 4006400400023 2.5300E-02 2.4260E+00 4006400400024 ENDCOMMON 3 0 4006400400025 DATA 2 1 4006400400026 DATA DATA-ERR 4006400400027 PRT/FIS PRT/FIS 4006400400028 3.8300E+00 1.6000E-01 4006400400029 ENDDATA 3 0 4006400400030 ENDSUBENT 29 0 4006400499999 SUBENT 40064005 20140709 41644006400500001 BIB 5 12 4006400500002 REACTION (98-CF-252(0,F),PR,NU) 4006400500003 MONITOR (92-U-235(N,F),PR,NU) 4006400500004 Prompt NU-BAR at fission by 4006400500005 thermal neutrons 4006400500006 ANALYSIS Measured neutron spectrum was integrated. 4006400500007 ERR-ANALYS (DATA-ERR) Error of relative measurements was 4006400500008 equal to about 3 percent. 4006400500009 Error of absolute NU-BAR is average-squared on five 4006400500010 series of measurements 4006400500011 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006400500012 The same data in Table 3 of C,70HELSINKI . 4006400500013 (DEP,40064026) Measured spectrum. 4006400500014 ENDBIB 12 0 4006400500015 COMMON 2 3 4006400500016 MONIT EN-NRM 4006400500017 PRT/FIS EV 4006400500018 2.4260E+00 0.0235 4006400500019 ENDCOMMON 3 0 4006400500020 DATA 2 1 4006400500021 DATA DATA-ERR 4006400500022 PRT/FIS PRT/FIS 4006400500023 3.7700E+00 8.0000E-02 4006400500024 ENDDATA 3 0 4006400500025 ENDSUBENT 24 0 4006400599999 SUBENT 40064006 20140709 41644006400600001 BIB 9 17 4006400600002 REACTION (90-TH-229(N,F),PR,NU) 4006400600003 INC-SOURCE (REAC) Reactor SM-2. 4006400600004 FACILITY (REAC) SM-2 reactor. 4006400600005 INC-SPECT Measurements were done with and without Cd. 4006400600006 Cadmium ratio 3. 4006400600007 SAMPLE About 15 microg on platinum backing. 4006400600008 MONITOR (92-U-235(N,F),PR,NU) 4006400600009 Prompt NU-BAR at fission by 4006400600010 thermal neutrons 4006400600011 ANALYSIS Measured neutron spectrum was integrated. 4006400600012 ERR-ANALYS (DATA-ERR) Error of relative measurements was equal4006400600013 to about 3 percent. 4006400600014 Error of absolute NU-BAR is average-squared on five 4006400600015 series of measurements 4006400600016 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006400600017 The same data in Table 3 of C,70HELSINKI . 4006400600018 (DEP,40064030) Measured spectrum. 4006400600019 ENDBIB 17 0 4006400600020 COMMON 2 3 4006400600021 EN MONIT 4006400600022 EV PRT/FIS 4006400600023 2.5300E-02 2.4260E+00 4006400600024 ENDCOMMON 3 0 4006400600025 DATA 2 1 4006400600026 DATA DATA-ERR 4006400600027 PRT/FIS PRT/FIS 4006400600028 2.0500E+00 1.0000E-01 4006400600029 ENDDATA 3 0 4006400600030 ENDSUBENT 29 0 4006400699999 SUBENT 40064007 20140709 41644006400700001 BIB 9 18 4006400700002 REACTION (94-PU-238(N,F),PR,NU) 4006400700003 FACILITY (REAC) SM-2 reactor. 4006400700004 INC-SOURCE (REAC) Reactor SM-2. 4006400700005 INC-SPECT Measurements were done with and without Cd. 4006400700006 Cadmium ratio 7. 4006400700007 SAMPLE Pu-238 was produced by alpha-decay of Cm-242. 4006400700008 100% Pu-238, 50 microg. 4006400700009 MONITOR (92-U-235(N,F),PR,NU) 4006400700010 Prompt NU-BAR at fission by 4006400700011 thermal neutrons 4006400700012 ANALYSIS Measured neutron spectrum was integrated. 4006400700013 ERR-ANALYS (DATA-ERR) Error of relative measurements was equal 4006400700014 to about 3 percent 4006400700015 Error of absolute NU-BAR is average-squared on five 4006400700016 series of measurements 4006400700017 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006400700018 The same data in Table 3 of C,70HELSINKI . 4006400700019 (DEP,40064029) Measured spectrum. 4006400700020 ENDBIB 18 0 4006400700021 COMMON 2 3 4006400700022 EN MONIT 4006400700023 EV PRT/FIS 4006400700024 2.5300E-02 2.4260E+00 4006400700025 ENDCOMMON 3 0 4006400700026 DATA 2 1 4006400700027 DATA DATA-ERR 4006400700028 PRT/FIS PRT/FIS 4006400700029 2.9200E+00 1.2000E-01 4006400700030 ENDDATA 3 0 4006400700031 ENDSUBENT 30 0 4006400799999 SUBENT 40064008 20160512 41764006400800001 BIB 9 17 4006400800002 REACTION (95-AM-242-M(N,F)0-NN-1,PR,KE) 4006400800003 Average kinetic energy of prompt neutrons. 4006400800004 FACILITY (REAC) SM-2 reactor. 4006400800005 INC-SOURCE (REAC) Reactor SM-2 4006400800006 INC-SPECT Measurements were done with and without Cd. 4006400800007 Cadmium ratio 20. 4006400800008 SAMPLE Am-241 - 88.97%, Am-242 - 1.03%, Am-243 - 10.00%. 4006400800009 30 microg. 4006400800010 ANALYSIS Derived from measured neutron spectrum. 4006400800011 ERR-ANALYS (DATA-ERR) Not specified. 4006400800012 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006400800013 The same data in Table 3 of C,70HELSINKI . 4006400800014 (DEP,40064027) Measured spectrum. 4006400800015 HISTORY (20120302A) REACTION was corrected 4006400800016 SF4-7=,,PR,KE,N -> 0-NN-1,PR,KE according to 4006400800017 comment of N.Otsuka (NDS IAEA). 4006400800018 (20160512A) SD:SF4=Am-242m1 -> Am-242m in REACTION code4006400800019 ENDBIB 17 0 4006400800020 COMMON 1 3 4006400800021 EN 4006400800022 EV 4006400800023 2.5300E-02 4006400800024 ENDCOMMON 3 0 4006400800025 DATA 2 1 4006400800026 DATA DATA-ERR 4006400800027 MEV MEV 4006400800028 2.1300E+00 5.0000E-02 4006400800029 ENDDATA 3 0 4006400800030 ENDSUBENT 29 0 4006400899999 SUBENT 40064009 20140709 41644006400900001 BIB 6 13 4006400900002 REACTION (96-CM-244(0,F)0-NN-1,PR,KE) 4006400900003 SAMPLE 20 microg. Produced by Pu-242 activation in SM-2 4006400900004 reactor. Am-243 and Pu-238 admixtures < 0.3% each. 4006400900005 Cm-244 - 96.38%, Cm-242 - 0.05%, 4006400900006 Cm-243 < 0.35%, Cm-245 - 1.75%, Cm-246 - 1.47%. 4006400900007 ANALYSIS Derived from measured neutron spectrum. 4006400900008 ERR-ANALYS (DATA-ERR) Not specified. 4006400900009 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006400900010 The same data in Table 3 of C,70HELSINKI . 4006400900011 (DEP,40064028) Measured spectrum. 4006400900012 HISTORY (20120302A) REACTION was corrected 4006400900013 ),,PR,KE,N) -> )0-NN-1,PR,KE) 4006400900014 according to comment of N.Otsuke (NDS IAEA). 4006400900015 ENDBIB 13 0 4006400900016 NOCOMMON 0 0 4006400900017 DATA 2 1 4006400900018 DATA DATA-ERR 4006400900019 MEV MEV 4006400900020 2.0700E+00 5.0000E-02 4006400900021 ENDDATA 3 0 4006400900022 ENDSUBENT 21 0 4006400999999 SUBENT 40064010 20140709 41644006401000001 BIB 7 12 4006401000002 REACTION (96-CM-245(N,F)0-NN-1,PR,KE) 4006401000003 FACILITY (REAC) SM-2 reactor. 4006401000004 INC-SOURCE (REAC) Reactor SM-2 4006401000005 ANALYSIS Derived from measured neutron spectrum. 4006401000006 ERR-ANALYS (DATA-ERR) Not specified. 4006401000007 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401000008 (SPSDD,40297005) Superseded by newer publication. 4006401000009 The same data in Table 3 of C,70HELSINKI . 4006401000010 (DEP,40064025) Measured spectrum. 4006401000011 HISTORY (20120302A) REACTION was corrected 4006401000012 ),,PR,KE,N) -> )0-NN-1,PR,KE) 4006401000013 according to comment of N.Otsuke (NDS IAEA). 4006401000014 ENDBIB 12 0 4006401000015 COMMON 1 3 4006401000016 EN 4006401000017 EV 4006401000018 2.5300E-02 4006401000019 ENDCOMMON 3 0 4006401000020 DATA 2 1 4006401000021 DATA DATA-ERR 4006401000022 MEV MEV 4006401000023 2.2500E+00 8.0000E-02 4006401000024 ENDDATA 3 0 4006401000025 ENDSUBENT 24 0 4006401099999 SUBENT 40064011 20140709 41644006401100001 BIB 5 9 4006401100002 REACTION (98-CF-252(0,F)0-NN-1,PR,KE) 4006401100003 ANALYSIS Derived from measured neutron spectrum. 4006401100004 ERR-ANALYS (DATA-ERR) Not specified. 4006401100005 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401100006 The same data in Table 3 of C,70HELSINKI . 4006401100007 (DEP,40064026) Measured spectrum. 4006401100008 HISTORY (20120302A) REACTION was corrected 4006401100009 ),,PR,KE,N) -> )0-NN-1,PR,KE) 4006401100010 according to comment of N.Otsuke (NDS IAEA). 4006401100011 ENDBIB 9 0 4006401100012 NOCOMMON 0 0 4006401100013 DATA 2 1 4006401100014 DATA DATA-ERR 4006401100015 MEV MEV 4006401100016 2.2200E+00 5.0000E-02 4006401100017 ENDDATA 3 0 4006401100018 ENDSUBENT 17 0 4006401199999 SUBENT 40064012 20140709 41644006401200001 BIB 9 14 4006401200002 REACTION (90-TH-229(N,F)0-NN-1,PR,KE) 4006401200003 FACILITY (REAC) SM-2 reactor. 4006401200004 INC-SOURCE (REAC) Reactor SM-2 4006401200005 INC-SPECT Measurements were done with and without Cd. 4006401200006 Cadmium ratio 3. 4006401200007 SAMPLE About 15 microg on platinum backing. 4006401200008 ANALYSIS Derived from measured neutron spectrum. 4006401200009 ERR-ANALYS (DATA-ERR) Not specified. 4006401200010 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401200011 The same data in Table 3 of C,70HELSINKI . 4006401200012 (DEP,40064030) Measured spectrum. 4006401200013 HISTORY (20120302A) REACTION was corrected 4006401200014 ),,PR,KE,N) -> )0-NN-1,PR,KE) 4006401200015 according to comment of N.Otsuke (NDS IAEA). 4006401200016 ENDBIB 14 0 4006401200017 COMMON 1 3 4006401200018 EN 4006401200019 EV 4006401200020 2.5300E-02 4006401200021 ENDCOMMON 3 0 4006401200022 DATA 2 1 4006401200023 DATA DATA-ERR 4006401200024 MEV MEV 4006401200025 1.8600E+00 6.0000E-02 4006401200026 ENDDATA 3 0 4006401200027 ENDSUBENT 26 0 4006401299999 SUBENT 40064013 20140709 41644006401300001 BIB 9 15 4006401300002 REACTION (94-PU-238(N,F)0-NN-1,PR,KE) 4006401300003 FACILITY (REAC) SM-2 reactor. 4006401300004 INC-SOURCE (REAC) Reactor SM-2 4006401300005 INC-SPECT Measurements were done with and without Cd. 4006401300006 Cadmium ratio 7. 4006401300007 SAMPLE Pu-238 was produced by alpha-decay of Cm-242. 4006401300008 100% Pu-238, 50 microg. 4006401300009 ANALYSIS Derived from measured neutron spectrum. 4006401300010 ERR-ANALYS (DATA-ERR) Not specified. 4006401300011 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401300012 The same data in Table 3 of C,70HELSINKI . 4006401300013 (DEP,40064029) Measured spectrum. 4006401300014 HISTORY (20120302A) REACTION was corrected 4006401300015 ),,PR,KE,N) -> )0-NN-1,PR,KE) 4006401300016 according to comment of N.Otsuke (NDS IAEA). 4006401300017 ENDBIB 15 0 4006401300018 COMMON 1 3 4006401300019 EN 4006401300020 EV 4006401300021 2.5300E-02 4006401300022 ENDCOMMON 3 0 4006401300023 DATA 2 1 4006401300024 DATA DATA-ERR 4006401300025 MEV MEV 4006401300026 2.0300E+00 6.0000E-02 4006401300027 ENDDATA 3 0 4006401300028 ENDSUBENT 27 0 4006401399999 SUBENT 40064014 20140709 41644006401400001 BIB 8 21 4006401400002 REACTION (96-CM-244(N,F),,SIG) 4006401400003 FACILITY (REAC) SM-2 reactor. 4006401400004 INC-SOURCE (REAC) Reactor SM-2. 4006401400005 SAMPLE 4 microg. Produced by short-time activation of Am-243. 4006401400006 Cm-244 - 95.40%, Cm-242 - 3.90%, 4006401400007 Cm-245 - 9.40%, Cm-246 - 0.30%. 4006401400008 20 microg. Produced by Pu-242 activation in SM-2 4006401400009 reactor. Am-243 and Pu-238 admixtures < 0.3% each. 4006401400010 Cm-244 - 96.38%, Cm-242 - 0.05%, 4006401400011 Cm-243 < 0.35%, Cm-245 - 1.75%, Cm-246 - 1.47%. 4006401400012 Measurements were done by two samples and with and 4006401400013 without Cd. Counts(fis/sec) : 4006401400014 Sample 1 Sample 2 4006401400015 Spontaneous fission 59.6 16.9 4006401400016 Thermal neutron fission 240 30 4006401400017 Therm.neutron fission with Cd 75 18.2 4006401400018 ASSUMED (ASSUM,96-CM-245(N,F),,SIG) for thermal neutrons. 4006401400019 ERR-ANALYS (DATA-ERR) Not specified. 4006401400020 STATUS (TABLE) Text, page 96 of J,AE,29,(2),95,1970. 4006401400021 Also text, page 187 of C,70HELSINKI . 4006401400022 HISTORY (20120302C) Subent was added. 4006401400023 ENDBIB 21 0 4006401400024 COMMON 2 3 4006401400025 EN ASSUM 4006401400026 EV B 4006401400027 2.5300E-02 1700. 4006401400028 ENDCOMMON 3 0 4006401400029 DATA 2 1 4006401400030 DATA DATA-ERR 4006401400031 B B 4006401400032 1. 1. 4006401400033 ENDDATA 3 0 4006401400034 ENDSUBENT 33 0 4006401499999 SUBENT 40064015 20160512 41764006401500001 BIB 9 15 4006401500002 REACTION (95-AM-242-M(N,F)0-NN-1,PR,KEM) 4006401500003 Temperature of measured prompt neutron spectrum. 4006401500004 FACILITY (REAC) SM-2 reactor. 4006401500005 INC-SOURCE (REAC) Reactor SM-2 4006401500006 INC-SPECT Measurements were done with and without Cd. 4006401500007 Cadmium ratio 20. 4006401500008 SAMPLE Am-241 - 88.97%, Am-242 - 1.03%, Am-243 - 10.00%. 4006401500009 30 microg. 4006401500010 ANALYSIS Derived from measured neutron spectrum approximated 4006401500011 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006401500012 ERR-ANALYS (DATA-ERR) Not specified. 4006401500013 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401500014 The same data in Table 3 of C,70HELSINKI . 4006401500015 (DEP,40064027) Measured spectrum. 4006401500016 HISTORY (20160512A) SD:SF4=Am-242m1 -> Am-242m in REACTION code4006401500017 ENDBIB 15 0 4006401500018 COMMON 1 3 4006401500019 EN 4006401500020 EV 4006401500021 2.5300E-02 4006401500022 ENDCOMMON 3 0 4006401500023 DATA 2 1 4006401500024 DATA DATA-ERR 4006401500025 MEV MEV 4006401500026 1.42 0.03 4006401500027 ENDDATA 3 0 4006401500028 ENDSUBENT 27 0 4006401599999 SUBENT 40064016 20140709 41644006401600001 BIB 4 8 4006401600002 REACTION (96-CM-244(0,F)0-NN-1,PR,KEM) 4006401600003 Temperature of measured prompt neutron spectrum. 4006401600004 ANALYSIS Derived from measured neutron spectrum approximated 4006401600005 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006401600006 ERR-ANALYS (DATA-ERR) Not specified. 4006401600007 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401600008 The same data in Table 3 of C,70HELSINKI . 4006401600009 (DEP,40064028) Measured spectrum. 4006401600010 ENDBIB 8 0 4006401600011 NOCOMMON 0 0 4006401600012 DATA 2 1 4006401600013 DATA DATA-ERR 4006401600014 MEV MEV 4006401600015 1.38 0.003 4006401600016 ENDDATA 3 0 4006401600017 ENDSUBENT 16 0 4006401699999 SUBENT 40064017 20140709 41644006401700001 BIB 6 11 4006401700002 REACTION (96-CM-245(N,F)0-NN-1,PR,KEM) 4006401700003 Temperature of measured prompt neutron spectrum. 4006401700004 FACILITY (REAC) SM-2 reactor. 4006401700005 INC-SOURCE (REAC) Reactor SM-2 4006401700006 ANALYSIS Derived from measured neutron spectrum approximated 4006401700007 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006401700008 ERR-ANALYS (DATA-ERR) Not specified. 4006401700009 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401700010 (SPSDD,40297005) 4006401700011 The same data in Table 3 of C,70HELSINKI . 4006401700012 (DEP,40064025) Measured spectrum. 4006401700013 ENDBIB 11 0 4006401700014 COMMON 1 3 4006401700015 EN 4006401700016 EV 4006401700017 0.0253 4006401700018 ENDCOMMON 3 0 4006401700019 DATA 2 1 4006401700020 DATA DATA-ERR 4006401700021 MEV MEV 4006401700022 1.50 0.05 4006401700023 ENDDATA 3 0 4006401700024 ENDSUBENT 23 0 4006401799999 SUBENT 40064018 20140709 41644006401800001 BIB 4 8 4006401800002 REACTION (98-CF-252(0,F)0-NN-1,PR,KEM) 4006401800003 Temperature of measured prompt neutron spectrum. 4006401800004 ANALYSIS Derived from measured neutron spectrum approximated 4006401800005 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006401800006 ERR-ANALYS (DATA-ERR) Not specified. 4006401800007 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401800008 The same data in Table 3 of C,70HELSINKI . 4006401800009 (DEP,40064026) Measured spectrum. 4006401800010 ENDBIB 8 0 4006401800011 NOCOMMON 0 0 4006401800012 DATA 2 1 4006401800013 DATA DATA-ERR 4006401800014 MEV MEV 4006401800015 1.48 0.03 4006401800016 ENDDATA 3 0 4006401800017 ENDSUBENT 16 0 4006401899999 SUBENT 40064019 20140709 41644006401900001 BIB 8 13 4006401900002 REACTION (90-TH-229(N,F)0-NN-1,PR,KEM) 4006401900003 Temperature of measured prompt neutron spectrum. 4006401900004 FACILITY (REAC) SM-2 reactor. 4006401900005 INC-SOURCE (REAC) Reactor SM-2 4006401900006 INC-SPECT Measurements were done with and without Cd. 4006401900007 Cadmium ratio 3. 4006401900008 SAMPLE About 15 microg on platinum backing. 4006401900009 ANALYSIS Derived from measured neutron spectrum approximated 4006401900010 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006401900011 ERR-ANALYS (DATA-ERR) Not specified. 4006401900012 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006401900013 The same data in Table 3 of C,70HELSINKI . 4006401900014 (DEP,40064030) Measured spectrum. 4006401900015 ENDBIB 13 0 4006401900016 COMMON 1 3 4006401900017 EN 4006401900018 EV 4006401900019 2.5300E-02 4006401900020 ENDCOMMON 3 0 4006401900021 DATA 2 1 4006401900022 DATA DATA-ERR 4006401900023 MEV MEV 4006401900024 1.24 0.04 4006401900025 ENDDATA 3 0 4006401900026 ENDSUBENT 25 0 4006401999999 SUBENT 40064020 20140709 41644006402000001 BIB 7 12 4006402000002 REACTION (94-PU-238(N,F)0-NN-1,PR,KEM) 4006402000003 Temperature of measured prompt neutron spectrum. 4006402000004 FACILITY (REAC) SM-2 reactor. 4006402000005 INC-SOURCE (REAC) Reactor SM-2 4006402000006 SAMPLE Pu-238 was produced by alpha-decay of Cm-242. 4006402000007 100% Pu-238, 50 microg. 4006402000008 ANALYSIS Derived from measured neutron spectrum approximated 4006402000009 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006402000010 ERR-ANALYS (DATA-ERR) Not specified. 4006402000011 STATUS (TABLE) Table 2 of J,AE,29,(2),95,1970. 4006402000012 The same data in Table 3 of C,70HELSINKI . 4006402000013 (DEP,40064029) Measured spectrum. 4006402000014 ENDBIB 12 0 4006402000015 COMMON 1 3 4006402000016 EN 4006402000017 EV 4006402000018 2.5300E-02 4006402000019 ENDCOMMON 3 0 4006402000020 DATA 2 1 4006402000021 DATA DATA-ERR 4006402000022 MEV MEV 4006402000023 1.35 0.04 4006402000024 ENDDATA 3 0 4006402000025 ENDSUBENT 24 0 4006402099999 SUBENT 40064021 20140709 41644006402100001 BIB 10 16 4006402100002 REACTION (98-CF-249(N,F),PR,NU) 4006402100003 MONITOR (92-U-235(N,F),PR,NU) 4006402100004 Prompt NU-BAR at fission by thermal neutrons 4006402100005 FACILITY (REAC) SM-2 reactor. 4006402100006 INC-SOURCE (REAC) Reactor SM-2 4006402100007 INC-SPECT Measurements were done with and without Cd. 4006402100008 SAMPLE Cf-249 sample was obtained as result of BETA-decay 4006402100009 of Bk-249. 4006402100010 ANALYSIS Measured neutron spectrum was integrated. 4006402100011 ERR-ANALYS (DATA-ERR) Error of relative measurements was 4006402100012 equal to about 3 percent. 4006402100013 Error of absolute NU-BAR is average-squared on five 4006402100014 series of measurements 4006402100015 STATUS (TABLE) Table 3 of C,70HELSINKI . 4006402100016 (DEP,40064024) Measured spectrum. 4006402100017 HISTORY (20140709C) Subent was added. 4006402100018 ENDBIB 16 0 4006402100019 COMMON 2 3 4006402100020 MONIT EN 4006402100021 PRT/FIS EV 4006402100022 2.426 0.0235 4006402100023 ENDCOMMON 3 0 4006402100024 DATA 2 1 4006402100025 DATA DATA-ERR 4006402100026 PRT/FIS PRT/FIS 4006402100027 4.60 0.21 4006402100028 ENDDATA 3 0 4006402100029 ENDSUBENT 28 0 4006402199999 SUBENT 40064022 20140709 41644006402200001 BIB 9 12 4006402200002 REACTION (98-CF-249(N,F)0-NN-1,PR,KE) 4006402200003 Average kinetic energy of prompt neutrons. 4006402200004 FACILITY (REAC) SM-2 reactor. 4006402200005 INC-SOURCE (REAC) Reactor SM-2 4006402200006 INC-SPECT Measurements were done with and without Cd. 4006402200007 SAMPLE Cf-249 sample was obtained as result of BETA-decay 4006402200008 of Bk-249. 4006402200009 ANALYSIS Derived from measured neutron spectrum. 4006402200010 ERR-ANALYS (DATA-ERR) Not specified. 4006402200011 STATUS (TABLE) Table 3 of C,70HELSINKI . 4006402200012 (DEP,40064024) Measured spectrum. 4006402200013 HISTORY (20140709C) Subent was added. 4006402200014 ENDBIB 12 0 4006402200015 COMMON 1 3 4006402200016 EN 4006402200017 EV 4006402200018 0.0235 4006402200019 ENDCOMMON 3 0 4006402200020 DATA 2 1 4006402200021 DATA DATA-ERR 4006402200022 MEV MEV 4006402200023 2.32 0.06 4006402200024 ENDDATA 3 0 4006402200025 ENDSUBENT 24 0 4006402299999 SUBENT 40064023 20140709 41644006402300001 BIB 9 13 4006402300002 REACTION (98-CF-249(N,F)0-NN-1,PR,KEM) 4006402300003 Temperature of measured prompt neutron spectrum. 4006402300004 FACILITY (REAC) SM-2 reactor. 4006402300005 INC-SOURCE (REAC) Reactor SM-2 4006402300006 INC-SPECT Measurements were done with and without Cd. 4006402300007 SAMPLE Cf-249 sample was obtained as result of BETA-decay 4006402300008 of Bk-249. 4006402300009 ANALYSIS Derived from measured neutron spectrum approximated 4006402300010 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006402300011 ERR-ANALYS (DATA-ERR) Not specified. 4006402300012 STATUS (TABLE) Table 3 of C,70HELSINKI . 4006402300013 (DEP,40064024) Measured spectrum. 4006402300014 HISTORY (20140709C) Subent was added. 4006402300015 ENDBIB 13 0 4006402300016 COMMON 1 3 4006402300017 EN 4006402300018 EV 4006402300019 0.0235 4006402300020 ENDCOMMON 3 0 4006402300021 DATA 2 1 4006402300022 DATA DATA-ERR 4006402300023 MEV MEV 4006402300024 1.55 0.04 4006402300025 ENDDATA 3 0 4006402300026 ENDSUBENT 25 0 4006402399999 SUBENT 40064024 20160512 41764006402400001 BIB 9 20 4006402400002 REACTION (95-AM-242-M(N,F),PR,NU/DE,,RRE/REL) 4006402400003 Measured prompt neutron spectrum as N(E)/sqrt(E) 4006402400004 FACILITY (REAC) SM-2 reactor. 4006402400005 INC-SOURCE (REAC) Reactor SM-2 4006402400006 INC-SPECT Measurements were done with and without Cd. 4006402400007 Cadmium ratio 20. 4006402400008 SAMPLE Am-241 - 88.97%, Am-242 - 1.03%, Am-243 - 10.00%. 4006402400009 30 microg. 4006402400010 MONITOR (92-U-235(N,F),PR,NU/DE) with kT=1.29 MeV . 4006402400011 Derived from measured neutron spectrum approximated 4006402400012 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006402400013 ERR-ANALYS (E-ERR-DIG) Digitizing error of E 4006402400014 (ERR-DIG) Digitizing error of DATA 4006402400015 Quantization error (one pixel): 4006402400016 scale X - 0.0073 MeV, scale Y - 0.29 % . 4006402400017 STATUS (CURVE) Fig.4 of C,70HELSINKI 4006402400018 HISTORY (20140709C) Subent was added. 4006402400019 (20140919A) MONITOR and KT-NRM were added according to 4006402400020 the comment of N.Otsuka (NDS,IAEA). 4006402400021 (20160512A) SD:SF4=Am-242m1 -> Am-242m in REACTION code4006402400022 ENDBIB 20 0 4006402400023 COMMON 4 3 4006402400024 EN E-ERR-DIG ERR-DIG KT-NRM 4006402400025 EV MEV PER-CENT MEV 4006402400026 0.0253 0.0084 0.866 1.29 4006402400027 ENDCOMMON 3 0 4006402400028 DATA 2 17 4006402400029 E DATA 4006402400030 MEV ARB-UNITS 4006402400031 0.4292 439.57 4006402400032 0.5465 410.96 4006402400033 0.6784 379.10 4006402400034 0.8250 342.75 4006402400035 0.9863 311.94 4006402400036 1.1840 267.31 4006402400037 1.3159 244.95 4006402400038 1.4479 227.47 4006402400039 1.6237 200.22 4006402400040 1.8508 171.55 4006402400041 2.1146 142.14 4006402400042 2.4665 115.38 4006402400043 2.8692 83.604 4006402400044 3.3093 66.050 4006402400045 3.9759 40.725 4006402400046 4.8183 22.102 4006402400047 5.9767 11.055 4006402400048 ENDDATA 19 0 4006402400049 ENDSUBENT 48 0 4006402499999 SUBENT 40064025 20140709 41644006402500001 BIB 5 13 4006402500002 REACTION (96-CM-244(0,F),PR,NU/DE,,RRE/REL) 4006402500003 Measured prompt neutron spectrum as N(E)/sqrt(E) 4006402500004 MONITOR (92-U-235(N,F),PR,NU/DE) with kT=1.29 MeV 4006402500005 Derived from measured neutron spectrum approximated 4006402500006 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006402500007 ERR-ANALYS (E-ERR-DIG) Digitizing error of E 4006402500008 (ERR-DIG) Digitizing error of DATA 4006402500009 Quantization error (one pixel): 4006402500010 scale X - 0.0073 MeV, scale Y - 0.29 % . 4006402500011 STATUS (CURVE) Fig.4 of C,70HELSINKI 4006402500012 HISTORY (20140709C) Subent was added. 4006402500013 (20140919A) MONITOR and KT-NRM were added according to 4006402500014 the comment of N.Otsuka (NDS,IAEA). 4006402500015 ENDBIB 13 0 4006402500016 COMMON 3 3 4006402500017 E-ERR-DIG ERR-DIG KT-NRM 4006402500018 MEV PER-CENT MEV 4006402500019 0.0084 0.866 1.29 4006402500020 ENDCOMMON 3 0 4006402500021 DATA 2 18 4006402500022 E DATA 4006402500023 MEV ARB-UNITS 4006402500024 0.33086 290.87 4006402500025 0.43359 277.45 4006402500026 0.58081 279.10 4006402500027 0.70473 231.41 4006402500028 0.90253 200.97 4006402500029 1.1882 162.11 4006402500030 1.3789 146.54 4006402500031 1.5108 134.28 4006402500032 1.7085 115.07 4006402500033 1.9215 107.52 4006402500034 2.1261 86.195 4006402500035 2.4342 72.843 4006402500036 2.7636 55.324 4006402500037 3.1522 44.603 4006402500038 3.6359 32.090 4006402500039 3.7817 26.078 4006402500040 4.2658 20.325 4006402500041 5.9866 5.2032 4006402500042 ENDDATA 20 0 4006402500043 ENDSUBENT 42 0 4006402599999 SUBENT 40064026 20140709 41644006402600001 BIB 7 15 4006402600002 REACTION (96-CM-245(N,F),PR,NU/DE,,RRE/REL) 4006402600003 Measured prompt neutron spectrum as N(E)/sqrt(E) 4006402600004 FACILITY (REAC) SM-2 reactor. 4006402600005 INC-SOURCE (REAC) Reactor SM-2 4006402600006 MONITOR (92-U-235(N,F),PR,NU/DE) with kT=1.29 MeV 4006402600007 Derived from measured neutron spectrum approximated 4006402600008 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006402600009 ERR-ANALYS (E-ERR-DIG) Digitizing error of E 4006402600010 (ERR-DIG) Digitizing error of DATA 4006402600011 Quantization error (one pixel): 4006402600012 scale X - 0.0073 MeV, scale Y - 0.29 % . 4006402600013 STATUS (CURVE) Fig.4 of C,70HELSINKI 4006402600014 HISTORY (20140709C) Subent was added. 4006402600015 (20140919A) MONITOR and KT-NRM were added according to 4006402600016 the comment of N.Otsuka (NDS,IAEA). 4006402600017 ENDBIB 15 0 4006402600018 COMMON 4 3 4006402600019 EN E-ERR-DIG ERR-DIG KT-NRM 4006402600020 EV MEV PER-CENT MEV 4006402600021 0.0253 0.0084 0.866 1.29 4006402600022 ENDCOMMON 3 0 4006402600023 DATA 2 17 4006402600024 E DATA 4006402600025 MEV ARB-UNITS 4006402600026 0.4403 795.69 4006402600027 0.5423 682.19 4006402600028 0.6228 637.92 4006402600029 0.7401 588.50 4006402600030 0.9896 528.26 4006402600031 1.1949 474.30 4006402600032 1.4514 395.63 4006402600033 1.5908 374.80 4006402600034 1.7519 329.93 4006402600035 1.9864 280.79 4006402600036 2.3017 234.14 4006402600037 2.5803 199.23 4006402600038 2.9834 153.29 4006402600039 3.5183 105.93 4006402600040 4.1119 71.256 4006402600041 4.9034 42.467 4006402600042 5.9366 21.113 4006402600043 ENDDATA 19 0 4006402600044 ENDSUBENT 43 0 4006402699999 SUBENT 40064027 20140709 41644006402700001 BIB 5 13 4006402700002 REACTION (98-CF-252(0,F),PR,NU/DE,,RRE/REL) 4006402700003 Measured prompt neutron spectrum as N(E)/sqrt(E) 4006402700004 MONITOR (92-U-235(N,F),PR,NU/DE) with kT=1.29 MeV 4006402700005 Derived from measured neutron spectrum approximated 4006402700006 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006402700007 ERR-ANALYS (E-ERR-DIG) Digitizing error of E 4006402700008 (ERR-DIG) Digitizing error of DATA 4006402700009 Quantization error (one pixel): 4006402700010 scale X - 0.0073 MeV, scale Y - 0.29 % . 4006402700011 STATUS (CURVE) Fig.4 of C,70HELSINKI 4006402700012 HISTORY (20140709C) Subent was added. 4006402700013 (20140919A) MONITOR and KT-NRM were added according to 4006402700014 the comment of N.Otsuka (NDS,IAEA). 4006402700015 ENDBIB 13 0 4006402700016 COMMON 3 3 4006402700017 E-ERR-DIG ERR-DIG KT-NRM 4006402700018 MEV PER-CENT MEV 4006402700019 0.0084 0.866 1.29 4006402700020 ENDCOMMON 3 0 4006402700021 DATA 2 17 4006402700022 E DATA 4006402700023 MEV ARB-UNITS 4006402700024 0.4743 512.31 4006402700025 0.6287 505.12 4006402700026 0.6947 485.14 4006402700027 0.7826 456.67 4006402700028 1.0324 426.66 4006402700029 1.2229 375.52 4006402700030 1.3769 341.78 4006402700031 1.5014 313.19 4006402700032 1.6920 277.50 4006402700033 1.8970 236.21 4006402700034 2.1681 194.40 4006402700035 2.5194 143.74 4006402700036 2.8712 114.38 4006402700037 3.3552 87.963 4006402700038 4.0511 53.154 4006402700039 4.8867 31.044 4006402700040 5.9860 15.224 4006402700041 ENDDATA 19 0 4006402700042 ENDSUBENT 41 0 4006402799999 SUBENT 40064028 20140709 41644006402800001 BIB 9 18 4006402800002 REACTION (90-TH-229(N,F),PR,NU/DE,,RRE/REL) 4006402800003 Measured prompt neutron spectrum as N(E)/sqrt(E) 4006402800004 FACILITY (REAC) SM-2 reactor. 4006402800005 INC-SOURCE (REAC) Reactor SM-2 4006402800006 INC-SPECT Measurements were done with and without Cd. 4006402800007 Cadmium ratio 3. 4006402800008 SAMPLE About 15 microg on platinum backing. 4006402800009 MONITOR (92-U-235(N,F),PR,NU/DE) with kT=1.29 MeV 4006402800010 Derived from measured neutron spectrum approximated 4006402800011 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006402800012 ERR-ANALYS (E-ERR-DIG) Digitizing error of E 4006402800013 (ERR-DIG) Digitizing error of DATA 4006402800014 Quantization error (one pixel): 4006402800015 scale X - 0.0073 MeV, scale Y - 0.29 % . 4006402800016 STATUS (CURVE) Fig.4 of C,70HELSINKI 4006402800017 HISTORY (20140709C) Subent was added. 4006402800018 (20140919A) MONITOR and KT-NRM were added according to 4006402800019 the comment of N.Otsuka (NDS,IAEA). 4006402800020 ENDBIB 18 0 4006402800021 COMMON 4 3 4006402800022 EN E-ERR-DIG ERR-DIG KT-NRM 4006402800023 EV MEV PER-CENT MEV 4006402800024 0.0253 0.0084 0.866 1.29 4006402800025 ENDCOMMON 3 0 4006402800026 DATA 2 20 4006402800027 E DATA 4006402800028 MEV ARB-UNITS 4006402800029 0.5243 125.42 4006402800030 0.5903 122.08 4006402800031 0.5983 134.02 4006402800032 0.6713 122.03 4006402800033 0.7591 113.34 4006402800034 0.8322 103.89 4006402800035 0.9347 95.852 4006402800036 1.0666 88.420 4006402800037 1.1544 81.584 4006402800038 1.3300 68.994 4006402800039 1.4183 68.962 4006402800040 1.6082 55.286 4006402800041 1.7839 48.018 4006402800042 2.0319 33.904 4006402800043 2.3326 28.845 4006402800044 3.0939 15.148 4006402800045 3.5559 11.651 4006402800046 4.2444 6.9939 4006402800047 5.1224 3.1069 4006402800048 6.2128 1.1985 4006402800049 ENDDATA 22 0 4006402800050 ENDSUBENT 49 0 4006402899999 SUBENT 40064029 20140709 41644006402900001 BIB 8 17 4006402900002 REACTION (94-PU-238(N,F),PR,NU/DE,,RRE/REL) 4006402900003 Measured prompt neutron spectrum as N(E)/sqrt(E) 4006402900004 FACILITY (REAC) SM-2 reactor. 4006402900005 INC-SOURCE (REAC) Reactor SM-2 4006402900006 SAMPLE Pu-238 was produced by alpha-decay of Cm-242. 4006402900007 100% Pu-238, 50 microg. 4006402900008 MONITOR (92-U-235(N,F),PR,NU/DE) with kT=1.29 MeV 4006402900009 Derived from measured neutron spectrum approximated 4006402900010 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006402900011 ERR-ANALYS (E-ERR-DIG) Digitizing error of E 4006402900012 (ERR-DIG) Digitizing error of DATA 4006402900013 Quantization error (one pixel): 4006402900014 scale X - 0.0073 MeV, scale Y - 0.29 % . 4006402900015 STATUS (CURVE) Fig.4 of C,70HELSINKI 4006402900016 HISTORY (20140709C) Subent was added. 4006402900017 (20140919A) MONITOR and KT-NRM were added according to 4006402900018 the comment of N.Otsuka (NDS,IAEA). 4006402900019 ENDBIB 17 0 4006402900020 COMMON 4 3 4006402900021 EN E-ERR-DIG ERR-DIG KT-NRM 4006402900022 EV MEV PER-CENT MEV 4006402900023 0.0253 0.0084 0.866 1.29 4006402900024 ENDCOMMON 3 0 4006402900025 DATA 2 22 4006402900026 E DATA 4006402900027 MEV ARB-UNITS 4006402900028 0.4170 205.55 4006402900029 0.5568 204.03 4006402900030 0.6371 184.53 4006402900031 0.7179 179.60 4006402900032 0.7915 181.94 4006402900033 0.8650 179.47 4006402900034 0.9381 165.60 4006402900035 0.9894 160.13 4006402900036 1.0777 160.06 4006402900037 1.2023 147.65 4006402900038 1.3193 131.75 4006402900039 1.4655 112.93 4006402900040 1.6048 103.48 4006402900041 1.8391 85.179 4006402900042 2.0224 76.999 4006402900043 2.2784 60.485 4006402900044 2.6008 48.135 4006402900045 3.0623 34.177 4006402900046 3.5897 23.462 4006402900047 4.2489 14.275 4006402900048 5.1276 7.1502 4006402900049 6.2196 3.5066 4006402900050 ENDDATA 24 0 4006402900051 ENDSUBENT 50 0 4006402999999 SUBENT 40064030 20140709 41644006403000001 BIB 9 18 4006403000002 REACTION (98-CF-249(N,F),PR,NU/DE,,RRE/REL) 4006403000003 Measured prompt neutron spectrum as N(E)/sqrt(E) 4006403000004 FACILITY (REAC) SM-2 reactor. 4006403000005 INC-SOURCE (REAC) Reactor SM-2 4006403000006 INC-SPECT Measurements were done with and without Cd. 4006403000007 SAMPLE Cf-249 sample was obtained as result of BETA-decay 4006403000008 of Bk-249. 4006403000009 MONITOR (92-U-235(N,F),PR,NU/DE) with kT=1.29 MeV 4006403000010 Derived from measured neutron spectrum approximated 4006403000011 as Maxwellian distribution sqrt(E)*exp(-E/T). 4006403000012 ERR-ANALYS (E-ERR-DIG) Digitizing error of E 4006403000013 (ERR-DIG) Digitizing error of DATA 4006403000014 Quantization error (one pixel): 4006403000015 scale X - 0.0073 MeV, scale Y - 0.29 % . 4006403000016 STATUS (CURVE) Fig.4 of C,70HELSINKI 4006403000017 HISTORY (20140709C) Subent was added. 4006403000018 (20140919A) MONITOR and KT-NRM were added according to 4006403000019 the comment of N.Otsuka (NDS,IAEA). 4006403000020 ENDBIB 18 0 4006403000021 COMMON 4 3 4006403000022 EN E-ERR-DIG ERR-DIG KT-NRM 4006403000023 EV MEV PER-CENT MEV 4006403000024 0.0253 0.0084 0.866 1.29 4006403000025 ENDCOMMON 3 0 4006403000026 DATA 2 22 4006403000027 E DATA 4006403000028 MEV ARB-UNITS 4006403000029 0.3979 1053.1 4006403000030 0.5301 1011.1 4006403000031 0.6328 964.48 4006403000032 0.7287 1003.4 4006403000033 0.8013 848.97 4006403000034 0.8751 877.41 4006403000035 0.9555 815.02 4006403000036 1.0799 722.37 4006403000037 1.1679 689.11 4006403000038 1.2414 679.72 4006403000039 1.4027 622.76 4006403000040 1.5123 552.01 4006403000041 1.7032 512.46 4006403000042 1.9085 454.02 4006403000043 2.1722 376.18 4006403000044 2.5094 303.36 4006403000045 2.8535 230.38 4006403000046 3.2859 173.72 4006403000047 3.7918 129.21 4006403000048 4.5028 81.801 4006403000049 5.4188 44.674 4006403000050 6.5114 23.893 4006403000051 ENDDATA 24 0 4006403000052 ENDSUBENT 51 0 4006403099999 ENDENTRY 30 0 4006499999999