ENTRY 22784 20081124 22062278400000001 SUBENT 22784001 20081124 22062278400100001 BIB 16 62 2278400100002 TITLE .Measurements of keV-neutron capture cross sections 2278400100003 and capture gamma-ray spectra of 143,145,146Nd 2278400100004 AUTHOR (T.Veerapaspong, M.Igashira, S.Mizuno, 2278400100005 Jun-Ichi Hori, T.Ohsaki) 2278400100006 INSTITUTE (2JPNTIT) Research Lab. for Nuclear Reactors 2278400100007 REFERENCE (J,NST,36,(10),855,199910) Main reference 2278400100008 (J,NST,36,(6),493,199906) Experimental and data 2278400100009 analysis details, error structure 2278400100010 FACILITY (VDGT,2JPNTIT) The 3.2 MV PELLETRON accelerator of the 2278400100011 research laboratory for nuclear reactors at the Tokyo 2278400100012 Institute of Technology. 2278400100013 INC-SPECT .Broad neutron spectrum measured by TOF method 2278400100014 PART-DET (G,N) 2278400100015 DETECTOR (NAICR) Anti-Compton Na-I(TL) spectrometer. Main 2278400100016 detector 15.2 cm diameter by 20.3 cm was centered 2278400100017 in a 33.0 cm outer diameter by 35.6 cm NaI(TL) hollow 2278400100018 Compton-suppression detector - for gamma detection 2278400100019 energy resolution is 7% at 0.662 MeV and time resolu- 2278400100020 tion is 4.0 ns for 0.511 MeV gamma. Spectrometer was 2278400100021 set at angle 125 degree with respect to the proton 2278400100022 beam direction. 2278400100023 (GLASD) Li-6 glass detector for neutron energy and 2278400100024 flux monitoring. 5 mm diameter * 5 mm length 6-Li 2278400100025 detector located 30 cm from neutron source was used 2278400100026 for 10-90 keV region, and 102 mm diameter * 6.4 mm 2278400100027 length detector located 460 cm from neutron source 2278400100028 was used for 550 keV 2278400100029 METHOD (TOF) Flight bases are 12 and 20 cm 2278400100030 (PHD) Pulse-height discrimination 2278400100031 (SITA) Cyclic sample-gold monitor-blanck irradiation 2278400100032 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) ENDF/B-VI data file 2278400100033 for 197-Au, MAT=7925, evaluated by 2278400100034 P.G.Young (1984) 2278400100035 ADD-RES (G-SPC) 2278400100036 SAMPLE .Gold sample for monitor, metallic, chemical purity 2278400100037 99.999%, weight 12.04 gram, thickness 2.0 mm/11.7e-3 2278400100038 nuclei/barn, diameter 20.0 mm 2278400100039 ERR-ANALYS (ERR-T) Total error composed of partial ones given 2278400100040 below 2278400100041 (ERR-S) Max statistical error 2278400100042 (MONIT-ERR) Error of the standard cross-section 2278400100043 (ERR-1) Max error of the response function 2278400100044 (ERR-2) Error due to the trial function 2278400100045 (ERR-3) Resultant error due to weighting function 2278400100046 (ERR-4) Error due to the extrapolation of gamma 2278400100047 spectrum 2278400100048 (ERR-5) Max error of sample chemical-impurity 2278400100049 content 2278400100050 (ERR-6) Max error of the multiplicity of observed 2278400100051 gamma-rays 2278400100052 .Error structure was taken from the second reference 2278400100053 CORRECTION .Corrections were made for neutron self-shielding and 2278400100054 multiple scattering in the sample, for gamma-ray 2278400100055 absorption and scattering in sample, for neutron cross2278400100056 sections employed in calculations. 2278400100057 Taken from second reference 2278400100058 STATUS (COREL,22482001) Experimental and analysis details 2278400100059 HISTORY (20001018C) + + Compiled by S.M. 2278400100060 (20080626U) BIB-information corrected. 2278400100061 SF8="SPA" changed to "AV" in SAN 002-004 - SM 2278400100062 (20080915A) Three SUBENTS added for EN = 550 keV 2278400100063 (20081124A) Nine SUBENTS added for gamma spectra data 2278400100064 ENDBIB 62 0 2278400100065 COMMON 8 6 2278400100066 MONIT-ERR ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2278400100067 ERR-6 ERR-S 2278400100068 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2278400100069 PER-CENT PER-CENT 2278400100070 3. 6. 2. 2. 2. 1.2278400100071 2. 4. 2278400100072 ENDCOMMON 6 0 2278400100073 ENDSUBENT 72 0 2278400199999 SUBENT 22784002 20080915 22012278400200001 BIB 7 22 2278400200002 REACTION (60-ND-143(N,G)60-ND-144,,SIG,,AV) Averaged over 2278400200003 neutron incident spectrum width 2278400200004 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278400200005 proton beam. Proton energy is 1.903 MeV (22 keV above 2278400200006 threshold energy of P-Li7 reaction), pulse repetition 2278400200007 rate 2 MHz, beam current 5.6 micro-A. 2278400200008 ANALYSIS .Measurements made without sample heating 2278400200009 SAMPLE .Nd2-O3 Oxide Powder in Graphite Container 24.0 mm 2278400200010 outer diameter and 4.0 mm wall thickness. 2278400200011 Powder weight is 1.164 gram, chemical purity 98.11%, 2278400200012 net weight 0.895+-0.008 gram, thickness 2.4 mm/ 2278400200013 (1.20+-0.01)e-3 nuclei/barn, diameter 20.0 mm. 2278400200014 Water content in sample is 3.6%. 2278400200015 Nd-142 content is 2.39%, Nd-143 content is 90.85%, 2278400200016 Nd-144 content is 4.51%, Nd-145 content is 0.58%, 2278400200017 Nd-146 content is 1.46%, Nd-148 content is 0.12%, 2278400200018 Nd-150 content is 0.09% 2278400200019 CORRECTION .Corrections not made for water content in samples 2278400200020 STATUS (TABLE) Table 4 of main reference 2278400200021 HISTORY (20080915C) SM. INC-SOURCE, ANALYSIS keywords added, 2278400200022 SAMPLE free text updated. DATA for EN=550 keV 2278400200023 moved to SUBENT 22784008 2278400200024 ENDBIB 22 0 2278400200025 NOCOMMON 0 0 2278400200026 DATA 4 4 2278400200027 EN-MIN EN-MAX DATA ERR-T 2278400200028 KEV KEV B B 2278400200029 14. 25. 0.296 0.013 2278400200030 25. 35. 0.226 0.010 2278400200031 35. 55. 0.181 0.007 2278400200032 55. 90. 0.147 0.006 2278400200033 ENDDATA 6 0 2278400200034 ENDSUBENT 33 0 2278400299999 SUBENT 22784003 20080915 22012278400300001 BIB 7 23 2278400300002 REACTION (60-ND-145(N,G)60-ND-146,,SIG,,AV) Averaged over 2278400300003 neutron incident spectrum width 2278400300004 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278400300005 proton beam. Proton energy is 1.903 MeV (22 keV above 2278400300006 threshold energy of P-Li7 reaction), pulse repetition 2278400300007 rate 2 MHz, beam current 4.5 micro-A. 2278400300008 ANALYSIS .Measurements made before and after sample heating 2278400300009 SAMPLE .Nd2-O3 Oxide Powder in Graphite Container 24.0 mm 2278400300010 outer diameter and 8 mm wall thickness. 2278400300011 Powder weight is 1.168 gram, chemical purity 98.53%, 2278400300012 net weight is 0.906+-0.007 gram, thickness 5.9 mm/ 2278400300013 Water content in sample is 11.7% before, 1.7% after 2278400300014 sample heating. 2278400300015 (1.20+-0.01)e-3 nuclei/barn, diameter 20.0 mm. 2278400300016 Nd-142 content is 0.92%, Nd-143 content is 0.78%, 2278400300017 Nd-144 content is 2.55%, Nd-145 content is 91.73%, 2278400300018 Nd-146 content is 3.67%, Nd-148 content is 0.28%, 2278400300019 Nd-150 content is 0.15% 2278400300020 CORRECTION .Corrections not made for water content in samples 2278400300021 STATUS (TABLE) Table 4 of main reference 2278400300022 HISTORY (20080915C) SM. INC-SOURCE, ANALYSIS keywords added, 2278400300023 SAMPLE free text updated. DATA for EN=550 keV 2278400300024 moved to SUBENT 22784009 2278400300025 ENDBIB 23 0 2278400300026 NOCOMMON 0 0 2278400300027 DATA 4 4 2278400300028 EN-MIN EN-MAX DATA ERR-T 2278400300029 KEV KEV B B 2278400300030 8. 15. 0.748 0.041 2278400300031 15. 25. 0.520 0.024 2278400300032 25. 45. 0.371 0.016 2278400300033 45. 90. 0.271 0.014 2278400300034 ENDDATA 6 0 2278400300035 ENDSUBENT 34 0 2278400399999 SUBENT 22784004 20080915 22012278400400001 BIB 7 22 2278400400002 REACTION (60-ND-146(N,G)60-ND-147,,SIG,,AV) Averaged over 2278400400003 neutron incident spectrum width 2278400400004 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278400400005 proton beam. Proton energy is 1.903 MeV (22 keV above 2278400400006 threshold energy of P-Li7 reaction), pulse repetition 2278400400007 rate 2 MHz, beam current 5.8 micro-A. 2278400400008 ANALYSIS .Measurements made only after sample heating 2278400400009 SAMPLE .Nd2-O3 oxide powder in graphite container 24.0 mm 2278400400010 outer diameter and 8.5 mm thickness. Powder weight is 2278400400011 1.179 gram, chemical purity 98.3%, net weight is 2278400400012 0.958+-0.008 gram, thickness 6.5 mm/ 2278400400013 (1.232+-0.010)e-3 nuclei/barn, diameter 20.0 mm. 2278400400014 Water content in sample is 0.2% after sample heating.2278400400015 Nd-142 content is 0.46%, Nd-143 content is 0.30%, 2278400400016 Nd-148 content is 0.68%, Nd-145 content is 0.49%, 2278400400017 Nd-146 content is 97.40%, Nd-148 content is 0.55%, 2278400400018 Nd-150 content is 0.12% 2278400400019 CORRECTION .Corrections not made for water content in samples 2278400400020 STATUS (TABLE) Table 4 of main reference 2278400400021 HISTORY (20080915C) SM. INC-SOURCE, ANALYSIS keywords added, 2278400400022 SAMPLE free text updated. DATA for EN=550 keV 2278400400023 moved to SUBENT 22784010 2278400400024 ENDBIB 22 0 2278400400025 NOCOMMON 0 0 2278400400026 DATA 4 3 2278400400027 EN-MIN EN-MAX DATA ERR-T 2278400400028 KEV KEV B B 2278400400029 20. 35. 0.087 0.005 2278400400030 35. 55. 0.074 0.004 2278400400031 55. 90. 0.071 0.003 2278400400032 ENDDATA 5 0 2278400400033 ENDSUBENT 32 0 2278400499999 SUBENT 22784005 20081124 22062278400500001 BIB 6 22 2278400500002 REACTION (60-ND-143(N,G)60-ND-144,PAR,MLT,,SPA) Gamma multip- 2278400500003 licity averaged over neutron incident spectrum width 2278400500004 EN-SEC (E-MIN,G) 2278400500005 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278400500006 proton beam. For neutron energies 10-90 keV proton 2278400500007 energy is 1.903 MeV (22 keV above threshold energy of 2278400500008 P-Li7 reaction), pulse repetition rate 2 MHz, beam 2278400500009 current 5.6 micro-A. For 550 keV neutron energy 2278400500010 proton energy is 2.3 MeV, pulse repetition rate 4 MHz,2278400500011 beam current 12.3 micro-A 2278400500012 MISC-COL (MISC1) Reduced gamma multiplicity MLT/RED defined as 2278400500013 MLT/((neutron binding energy in target)+ EN) 2278400500014 units=gamma-rays-number/1-MeV-excitation-energy/ 2278400500015 one-gamma-capture 2278400500016 (MISC2) Neutron binding energy 2278400500017 STATUS (TABLE) Table 5 of main reference 2278400500018 (DEP,22784002) Sample, Analysis --> 2278400500019 (DEP,22784008) are from these SUBENT 2278400500020 (DEP,22784012) 2278400500021 (DEP,22784013) 2278400500022 HISTORY (20080626U) E-MIN instead of Q-VAL, MISC2 for Q-VAL 2278400500023 INC-SOURCE keyword moved from SAN 001 2278400500024 ENDBIB 22 0 2278400500025 COMMON 2 3 2278400500026 E-MIN MISC2 2278400500027 MEV MEV 2278400500028 0.6 7.817 2278400500029 ENDCOMMON 3 0 2278400500030 DATA 6 2 2278400500031 EN-MEAN EN-RSL-FW DATA ERR-T MISC1 MISC1-ERR 2278400500032 KEV KEV PRT/REAC PRT/REAC SEE TEXT SEE TEXT 2278400500033 50. 3.82 0.15 0.485 0.0192278400500034 550. 104. 3.85 0.17 0.460 0.0202278400500035 ENDDATA 4 0 2278400500036 ENDSUBENT 35 0 2278400599999 SUBENT 22784006 20081124 22062278400600001 BIB 6 22 2278400600002 REACTION (60-ND-145(N,G)60-ND-146,PAR,MLT,,SPA) Gamma multip- 2278400600003 licity averaged over neutron incident spectrum width 2278400600004 EN-SEC (E-MIN,G) 2278400600005 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278400600006 proton beam. For neutron energies 10-90 keV proton 2278400600007 energy is 1.903 MeV (22 keV above threshold energy of 2278400600008 P-Li7 reaction), pulse repetition rate 2 MHz, beam 2278400600009 current 4.5 micro-A. For 550 keV neutron energy 2278400600010 proton energy is 2.3 MeV, pulse repetition rate 4 MHz,2278400600011 beam current 12.1 micro-A 2278400600012 MISC-COL (MISC1) Reduced gamma multiplicity MLT/RED defined as 2278400600013 MLT/((neutron binding energy in target)+ EN) 2278400600014 units=gamma-rays-number/1-MeV-excitation-energy/ 2278400600015 one-gamma-capture 2278400600016 (MISC2) Neutron binding energy 2278400600017 STATUS (TABLE) Table 5 of main reference 2278400600018 (DEP,22784003) Sample, Analysis 2278400600019 (DEP,22784009) are from these SUBENT 2278400600020 (DEP,22784015) 2278400600021 (DEP,22784016) 2278400600022 HISTORY (20080626U) E-MIN instead of Q-VAL, MISC2 for Q-VAL 2278400600023 INC-SOURCE keyword moved from SAN 001 2278400600024 ENDBIB 22 0 2278400600025 COMMON 2 3 2278400600026 E-MIN MISC2 2278400600027 MEV MEV 2278400600028 0.6 7.565 2278400600029 ENDCOMMON 3 0 2278400600030 DATA 6 2 2278400600031 EN-MEAN EN-RSL-FW DATA ERR-T MISC1 MISC1-ERR 2278400600032 KEV KEV PRT/REAC PRT/REAC SEE TEXT SEE TEXT 2278400600033 50. 3.82 0.15 0.502 0.0192278400600034 550. 100. 3.87 0.20 0.477 0.0242278400600035 ENDDATA 4 0 2278400600036 ENDSUBENT 35 0 2278400699999 SUBENT 22784007 20081124 22062278400700001 BIB 6 22 2278400700002 REACTION (60-ND-146(N,G)60-ND-147,PAR,MLT,,SPA) Gamma multip- 2278400700003 licity averaged over neutron incident spectrum width 2278400700004 EN-SEC (E-MIN,G) 2278400700005 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278400700006 proton beam. For neutron energies 10-90 keV proton 2278400700007 energy is 1.903 MeV (22 keV above threshold energy of 2278400700008 P-Li7 reaction), pulse repetition rate 2 MHz, beam 2278400700009 current 5.8 micro-A. For 550 keV neutron energy 2278400700010 proton energy is 2.3 MeV, pulse repetition rate 4 MHz,2278400700011 beam current 12.5 micro-A 2278400700012 MISC-COL (MISC1) Reduced gamma multiplicity MLT/RED defined as 2278400700013 MLT/((NEUTRON binding energy in target)+ EN) 2278400700014 Units=Gamma-Rays-Number/1MeV excitation-energy/ 2278400700015 one-gamma-capture 2278400700016 (MISC2) Neutron binding energy 2278400700017 STATUS (TABLE) Table 5 of main reference 2278400700018 (DEP,22784004) Sample, Analysis 2278400700019 (DEP,22784010) are from these SUBENT 2278400700020 (DEP,22784017) 2278400700021 (DEP,22784018) 2278400700022 HISTORY (20080626U) E-MIN instead of Q-VAL, MISC2 for Q-VAL 2278400700023 INC-SOURCE keyword moved from SAN 001 2278400700024 ENDBIB 22 0 2278400700025 COMMON 2 3 2278400700026 E-MIN MISC2 2278400700027 MEV MEV 2278400700028 0.6 5.292 2278400700029 ENDCOMMON 3 0 2278400700030 DATA 6 2 2278400700031 EN-MEAN EN-RSL-FW DATA ERR-T MISC1 MISC1-ERR 2278400700032 KEV KEV PRT/REAC PRT/REAC SEE TEXT SEE TEXT 2278400700033 50. 2.47 0.10 0.462 0.0192278400700034 550. 70. 2.68 0.13 0.459 0.0222278400700035 ENDDATA 4 0 2278400700036 ENDSUBENT 35 0 2278400799999 SUBENT 22784008 20081124 22062278400800001 BIB 4 8 2278400800002 REACTION (60-ND-143(N,G)60-ND-144,,SIG,,SPA) Averaged over 2278400800003 neutron incident spectrum width 2278400800004 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278400800005 proton beam. Proton energy is 2.3 MeV, pulse 2278400800006 repetition rate 4 MHz, beam current 12.3 micro-A 2278400800007 STATUS (TABLE) Table 4 of main reference 2278400800008 (DEP,22784002) Sample, Analysis are from this SUBENT 2278400800009 HISTORY (20080915C) SM 2278400800010 ENDBIB 8 0 2278400800011 NOCOMMON 0 0 2278400800012 DATA 4 1 2278400800013 EN-MEAN EN-RSL-FW DATA ERR-T 2278400800014 KEV KEV B B 2278400800015 550. 104. 0.061 0.004 2278400800016 ENDDATA 3 0 2278400800017 ENDSUBENT 16 0 2278400899999 SUBENT 22784009 20081124 22062278400900001 BIB 4 8 2278400900002 REACTION (60-ND-145(N,G)60-ND-146,,SIG,,SPA) Averaged over 2278400900003 neutron incident spectrum width 2278400900004 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278400900005 proton beam. Proton energy is 2.3 MeV, pulse 2278400900006 repetition rate 4 MHz, beam current 12.1 micro-A 2278400900007 STATUS (TABLE) Table 4 of main reference 2278400900008 (DEP,22784003) Sample, Analysis are from this SUBENT 2278400900009 HISTORY (20080915C) SM 2278400900010 ENDBIB 8 0 2278400900011 NOCOMMON 0 0 2278400900012 DATA 4 1 2278400900013 EN-MEAN EN-RSL-FW DATA ERR-T 2278400900014 KEV KEV B B 2278400900015 550. 100. 0.085 0.004 2278400900016 ENDDATA 3 0 2278400900017 ENDSUBENT 16 0 2278400999999 SUBENT 22784010 20081124 22062278401000001 BIB 4 8 2278401000002 REACTION (60-ND-146(N,G)60-ND-147,,SIG,,SPA) Averaged over 2278401000003 neutron incident spectrum width 2278401000004 INC-SOURCE (P-LI7) Lithium target bombarded by 1.5 ns bunched 2278401000005 proton beam. Proton energy is 2.3 MeV, pulse 2278401000006 repetition rate 4 MHz, beam current 12.5 micro-A 2278401000007 STATUS (TABLE) Table 4 of main reference 2278401000008 (DEP,22784004) Sample, Analysis are from this SUBENT 2278401000009 HISTORY (20080915C) SM 2278401000010 ENDBIB 8 0 2278401000011 NOCOMMON 0 0 2278401000012 DATA 4 1 2278401000013 EN-MEAN EN-RSL-FW DATA ERR-T 2278401000014 KEV KEV B B 2278401000015 550. 70. 0.038 0.002 2278401000016 ENDDATA 3 0 2278401000017 ENDSUBENT 16 0 2278401099999 SUBENT 22784011 20081124 22062278401100001 BIB 5 9 2278401100002 REACTION (60-ND-143(N,G)60-ND-144,,MLT/DE,,AV) Averaged 2278401100003 over neutron energy interval 2278401100004 EN-SEC (E,G) E-RSL is gamma ray energy bin 2278401100005 ERR-ANALYS (E-ERR-DIG) Secongary gamma energy digitizing error 2278401100006 (ERR-DIG) Data digi9izing error 2278401100007 (DATA-ERR) Error from the graphic bars 2278401100008 STATUS (CURVE) Fig.10 of main reference (Nd-143, 15-90keV) 2278401100009 (DEP,22784002) Sample, N-Source, Analysis 2278401100010 HISTORY (20081124C) SM 2278401100011 ENDBIB 9 0 2278401100012 COMMON 5 3 2278401100013 EN-MIN EN-MAX E-RSL E-ERR-DIG ERR-DIG 2278401100014 KEV KEV KEV MEV PT/RCT/MEV 2278401100015 15. 90. 50. 9.5631E-03 4.3738E-03 2278401100016 ENDCOMMON 3 0 2278401100017 DATA 3 118 2278401100018 E DATA DATA-ERR 2278401100019 MEV PT/RCT/MEV PT/RCT/MEV 2278401100020 0.59065 3.2389 0.42106 2278401100021 0.64315 6.5476 0.297 2278401100022 0.70166 7.3517 0.33321 2278401100023 0.74909 1.3608 0.22183 2278401100024 0.79091 2.3204 0.18923 2278401100025 0.84647 1.6127 0.14326 2278401100026 0.90089 0.93084 0.11472 2278401100027 0.96942 1.1118 0.15939 2278401100028 0.98874 1.1204 0.16737 2278401100029 1.0545 0.84779 0.12151 2278401100030 1.1118 0.79059 0.12888 2278401100031 1.1525 1.111 0.10809 2278401100032 1.2192 0.99671 8.8540E-02 2278401100033 1.2864 0.95124 7.0822E-02 2278401100034 1.3637 0.98846 0.10827 2278401100035 1.4321 1.1625 0.12301 2278401100036 1.5087 1.0757 9.5371E-02 2278401100037 1.6049 1.0506 9.3325E-02 2278401100038 1.6818 1.0182 5.3679E-02 2278401100039 1.7685 1.0101 6.7940E-02 2278401100040 1.7971 0.97161 9.2971E-02 2278401100041 1.8745 1.0175 5.6623E-02 2278401100042 1.961 0.99378 4.7220E-02 2278401100043 2.0379 0.95578 6.8925E-02 2278401100044 2.0954 0.9193 7.3949E-02 2278401100045 2.1725 0.91902 7.3926E-02 2278401100046 2.2592 0.9187 6.6251E-02 2278401100047 2.3362 0.91134 6.5682E-02 2278401100048 2.3842 0.87659 7.0514E-02 2278401100049 2.4221 0.79259 5.7157E-02 2278401100050 2.4794 0.73341 6.5151E-02 2278401100051 2.5468 0.72757 6.4509E-02 2278401100052 2.6335 0.72732 4.0446E-02 2278401100053 2.7297 0.71036 5.1226E-02 2278401100054 2.787 0.65732 6.9580E-02 2278401100055 2.8348 0.61775 4.9667E-02 2278401100056 2.9117 0.60339 2.8670E-02 2278401100057 2.9882 0.54973 3.0593E-02 2278401100058 3.0651 0.53281 3.4021E-02 2278401100059 3.1127 0.48925 3.5281E-02 2278401100060 3.1609 0.48915 5.0215E-02 2278401100061 3.238 0.489 3.9315E-02 2278401100062 3.3051 0.4667 2.5972E-02 2278401100063 3.3627 0.45237 3.2622E-02 2278401100064 3.4009 0.42188 3.1395E-02 2278401100065 3.4192 0.36418 2.9699E-02 2278401100066 3.4195 0.37854 3.6828E-02 2278401100067 3.4866 0.35849 1.9950E-02 2278401100068 3.5251 0.35844 2.6673E-02 2278401100069 3.5922 0.34209 2.4669E-02 2278401100070 3.6402 0.3316 2.9401E-02 2278401100071 3.7071 0.30446 1.8273E-02 2278401100072 3.7647 0.29284 1.7565E-02 2278401100073 3.8419 0.29963 1.9131E-02 2278401100074 3.89 0.29497 1.8822E-02 2278401100075 3.9476 0.28814 1.9381E-02 2278401100076 4.0148 0.27713 1.3168E-02 2278401100077 4.0919 0.27491 1.7553E-02 2278401100078 4.1397 0.26239 2.3309E-02 2278401100079 4.1878 0.25632 1.8484E-02 2278401100080 4.2457 0.26026 2.1233E-02 2278401100081 4.3035 0.26222 2.3293E-02 2278401100082 4.4089 0.23703 2.5972E-02 2278401100083 4.4476 0.24444 2.3381E-02 2278401100084 4.4959 0.2482 2.4158E-02 2278401100085 4.5631 0.24058 1.7349E-02 2278401100086 4.6107 0.2192 1.5799E-02 2278401100087 4.6488 0.20443 1.6436E-02 2278401100088 4.6966 0.19361 1.5789E-02 2278401100089 4.7543 0.18913 1.5423E-02 2278401100090 4.8314 0.18907 1.2717E-02 2278401100091 4.9085 0.19048 1.5540E-02 2278401100092 4.995 0.18461 1.3306E-02 2278401100093 5.052 0.16182 1.2059E-02 2278401100094 5.1184 0.13752 1.3159E-02 2278401100095 5.1663 0.13024 1.6052E-02 2278401100096 5.2145 0.13123 1.2557E-02 2278401100097 5.2919 0.13957 1.1227E-02 2278401100098 5.3681 0.12045 9.6891E-03 2278401100099 5.4147 9.3292E-02 6.7238E-03 2278401100100 5.4715 7.9283E-02 9.2314E-03 2278401100101 5.5199 8.3035E-02 8.5241E-03 2278401100102 5.5588 8.7642E-02 7.7706E-03 2278401100103 5.6074 9.3221E-02 6.2737E-03 2278401100104 5.6366 9.8397E-02 4.6794E-03 2278401100105 5.6565 0.1088 7.8460E-03 2278401100106 5.7443 0.12995 9.3709E-03 2278401100107 5.8202 0.10789 1.0497E-02 2278401100108 5.8659 7.2141E-02 9.3784E-03 2278401100109 5.93 4.1962E-02 8.6920E-03 2278401100110 5.975 2.4983E-02 8.6586E-03 2278401100111 6.0696 1.8757E-02 5.9183E-03 2278401100112 6.1294 2.6154E-02 7.2569E-03 2278401100113 6.2084 3.5907E-02 7.4355E-03 2278401100114 6.2676 4.4582E-02 7.4608E-03 2278401100115 6.318 6.4619E-02 8.8338E-03 2278401100116 6.3776 8.6017E-02 8.8302E-03 2278401100117 6.4456 9.4360E-02 9.9883E-03 2278401100118 6.503 8.8676E-02 1.0141E-02 2278401100119 6.5606 8.5954E-02 7.6319E-03 2278401100120 6.608 7.5346E-02 6.6932E-03 2278401100121 6.6739 5.8806E-02 6.7274E-03 2278401100122 6.7201 4.2813E-02 6.7797E-03 2278401100123 6.7758 3.0218E-02 7.1694E-03 2278401100124 6.8218 2.1495E-02 6.8969E-03 2278401100125 6.8868 1.4261E-02 6.5210E-03 2278401100126 6.9409 7.9191E-03 5.4761E-03 2278401100127 6.9546 3.1780E-03 2.1822E-03 2278401100128 7.026 6.0853E-03 3.6431E-03 2278401100129 7.0717 1.9270E-02 5.0343E-03 2278401100130 7.1242 3.8954E-02 6.8508E-03 2278401100131 7.165 5.6464E-02 7.7191E-03 2278401100132 7.2138 6.2912E-02 6.6568E-03 2278401100133 7.2613 5.6443E-02 6.9563E-03 2278401100134 7.3175 4.3378E-02 6.0975E-03 2278401100135 7.3635 3.0618E-02 5.1240E-03 2278401100136 7.419 2.0952E-02 5.4581E-03 2278401100137 7.4553 1.4676E-02 6.1377E-03 2278401100138 ENDDATA 120 0 2278401100139 ENDSUBENT 138 0 2278401199999 SUBENT 22784012 20081124 22062278401200001 BIB 5 9 2278401200002 REACTION (60-ND-143(N,G)60-ND-144,,MLT/DE,,SPA) Averaged 2278401200003 over neutron energy interval 2278401200004 EN-SEC (E,G) E-RSL is gamma ray energy bin 2278401200005 ERR-ANALYS (E-ERR-DIG) Secongary gamma energy digitizing error 2278401200006 (ERR-DIG) Data digitizing error 2278401200007 (DATA-ERR) Error from the graphic bars 2278401200008 STATUS (CURVE) Fig.10 of main reference (Nd-143, 550 keV) 2278401200009 (DEP,22784008) Sample, N-Source, Analysis 2278401200010 HISTORY (20081124C) SM 2278401200011 ENDBIB 9 0 2278401200012 COMMON 5 3 2278401200013 EN-MEAN EN-RSL E-RSL E-ERR-DIG ERR-DIG 2278401200014 KEV KEV KEV MEV PT/RCT/MEV 2278401200015 550. 104. 100. 1.0043E-02 2.4553E-03 2278401200016 ENDCOMMON 3 0 2278401200017 DATA 3 78 2278401200018 E DATA DATA-ERR 2278401200019 MEV PT/RCT/MEV PT/RCT/MEV 2278401200020 0.6056 2.0466 0.30596 2278401200021 0.71385 2.8942 0.23537 2278401200022 0.80354 4.5599 0.3384 2278401200023 0.90288 1.6598 0.20398 2278401200024 1.0063 1.1196 0.2034 2278401200025 1.1205 0.90179 0.2133 2278401200026 1.2179 1.0681 0.26511 2278401200027 1.3138 0.99606 0.16828 2278401200028 1.4104 1.0428 0.16271 2278401200029 1.5074 1.1434 0.18042 2278401200030 1.6128 1.05 0.14309 2278401200031 1.7097 1.1425 0.12046 2278401200032 1.8057 1.082 0.11822 2278401200033 1.9015 1.0013 0.10557 2278401200034 2.0167 0.94822 0.1036 2278401200035 2.1033 0.9262 9.4812E-02 2278401200036 2.2092 0.91162 0.10581 2278401200037 2.3152 0.91826 0.119 2278401200038 2.4208 0.87636 8.4961E-02 2278401200039 2.5165 0.79245 6.3523E-02 2278401200040 2.6121 0.70019 7.9850E-02 2278401200041 2.7174 0.63312 6.9153E-02 2278401200042 2.8039 0.61367 6.2797E-02 2278401200043 2.9289 0.59932 6.1328E-02 2278401200044 3.0155 0.58993 5.2222E-02 2278401200045 3.1211 0.55013 5.6295E-02 2278401200046 3.2166 0.48985 5.0126E-02 2278401200047 3.322 0.44293 5.0512E-02 2278401200048 3.4181 0.4293 4.6890E-02 2278401200049 3.5139 0.39728 4.6125E-02 2278401200050 3.6189 0.34035 4.8641E-02 2278401200051 3.7242 0.31013 4.6365E-02 2278401200052 3.8203 0.29599 4.2322E-02 2278401200053 3.9161 0.27391 3.9147E-02 2278401200054 4.0219 0.26753 3.8234E-02 2278401200055 4.1184 0.27368 3.7298E-02 2278401200056 4.2242 0.2673 3.6428E-02 2278401200057 4.3293 0.23436 3.3502E-02 2278401200058 4.4153 0.20868 3.2561E-02 2278401200059 4.5307 0.20381 3.1801E-02 2278401200060 4.6369 0.20849 3.3883E-02 2278401200061 4.7232 0.19746 2.9400E-02 2278401200062 4.829 0.19138 3.1102E-02 2278401200063 4.925 0.18265 3.4336E-02 2278401200064 5.0404 0.17702 3.3277E-02 2278401200065 5.1361 0.16007 3.0091E-02 2278401200066 5.2426 0.17416 2.9430E-02 2278401200067 5.3201 0.18662 2.7906E-02 2278401200068 5.425 0.15743 2.7602E-02 2278401200069 5.5281 0.10139 2.6334E-02 2278401200070 5.6419 7.6779E-02 2.4157E-02 2278401200071 5.7305 0.10288 2.5537E-02 2278401200072 5.8277 0.11724 2.5641E-02 2278401200073 5.9324 9.6644E-02 2.7806E-02 2278401200074 6.0277 8.2163E-02 2.0868E-02 2278401200075 6.1251 9.7314E-02 1.9503E-02 2278401200076 6.2299 8.1462E-02 2.1621E-02 2278401200077 6.3227 4.7099E-02 2.2264E-02 2278401200078 6.4261 3.2265E-02 2.4867E-02 2278401200079 6.5225 3.2252E-02 2.3422E-02 2278401200080 6.6234 1.5025E-02 8.1827E-03 2278401200081 6.7169 9.6776E-03 8.0849E-03 2278401200082 6.8335 4.9224E-02 2.4822E-02 2278401200083 6.9254 0.10804 2.9282E-02 2278401200084 7.0229 0.12797 2.7213E-02 2278401200085 7.1172 9.4692E-02 2.1021E-02 2278401200086 7.2289 5.2269E-02 2.9716E-02 2278401200087 7.3244 4.5477E-02 1.9174E-02 2278401200088 7.4228 6.2361E-02 1.0934E-02 2278401200089 7.5202 7.3861E-02 2.2054E-02 2278401200090 7.6156 6.3769E-02 5.9445E-02 2278401200091 7.7292 4.7184E-02 3.9995E-02 2278401200092 7.816 4.7532E-02 2.1686E-02 2278401200093 7.9228 5.4165E-02 1.2492E-02 2278401200094 8.0204 6.5150E-02 8.0042E-03 2278401200095 8.1265 6.7161E-02 6.4060E-03 2278401200096 8.2307 5.1253E-02 5.5981E-03 2278401200097 8.3128 2.5204E-02 2.4033E-02 2278401200098 ENDDATA 80 0 2278401200099 ENDSUBENT 98 0 2278401299999 SUBENT 22784013 20081119 22062278401300001 BIB 5 9 2278401300002 REACTION (60-ND-145(N,G)60-ND-146,,MLT/DE,,SPA) Averaged 2278401300003 over neutron energy interval 2278401300004 EN-SEC (E,G) E-RSL is gamma ray energy bin 2278401300005 ERR-ANALYS (E-ERR-DIG) Secongary gamma energy digitizing error 2278401300006 (ERR-DIG) Data digi9izing error 2278401300007 (DATA-ERR) Error from the graphic bars 2278401300008 STATUS (CURVE) Fig.10 of main reference (Nd-145, 15-90keV) 2278401300009 (DEP,22784003) Sample, N-Source, Analysis 2278401300010 HISTORY (20081124C) SM 2278401300011 ENDBIB 9 0 2278401300012 COMMON 5 3 2278401300013 EN-MIN EN-MAX E-RSL E-ERR-DIG ERR-DIG 2278401300014 KEV KEV KEV MEV PT/RCT/MEV 2278401300015 15. 90. 50. 5.6156E-03 1.3512E-03 2278401300016 ENDCOMMON 3 0 2278401300017 DATA 3 124 2278401300018 E DATA DATA-ERR 2278401300019 MEV PT/RCT/MEV PT/RCT/MEV 2278401300020 0.58237 1.3999 0.21098 2278401300021 0.6377 5.766 0.30558 2278401300022 0.69682 7.6876 0.35056 2278401300023 0.73614 1.4211 0.22353 2278401300024 0.78698 2.4493 0.21821 2278401300025 0.82344 1.6728 0.13713 2278401300026 0.90865 1.314 0.18578 2278401300027 0.98481 1.1509 0.196 2278401300028 1.0423 1.1242 0.2202 2278401300029 1.0995 1.0238 0.20035 2278401300030 1.1384 1.1151 0.24991 2278401300031 1.2248 1.1061 0.15639 2278401300032 1.2921 1.1232 0.13897 2278401300033 1.4171 1.1582 0.15133 2278401300034 1.4749 1.1946 0.14785 2278401300035 1.5514 1.1222 9.0781E-02 2278401300036 1.6279 1.0461 0.10058 2278401300037 1.7145 1.0622 8.5923E-02 2278401300038 1.7818 1.0786 8.8420E-02 2278401300039 1.83 1.1125 0.13768 2278401300040 1.9069 1.1296 0.12021 2278401300041 1.9739 1.0863 6.9711E-02 2278401300042 2.0508 1.0776 8.7171E-02 2278401300043 2.0987 1.0526 6.7584E-02 2278401300044 2.1465 1.0202 6.5467E-02 2278401300045 2.204 0.98105 7.1110E-02 2278401300046 2.2612 0.91454 5.8720E-02 2278401300047 2.3379 0.87942 9.6879E-02 2278401300048 2.3854 0.78855 5.7185E-02 2278401300049 2.4334 0.78843 5.0623E-02 2278401300050 2.5005 0.7641 4.9061E-02 2278401300051 2.5674 0.72344 5.4142E-02 2278401300052 2.6056 0.69036 6.1526E-02 2278401300053 2.6824 0.67953 5.4945E-02 2278401300054 2.7399 0.66891 5.9614E-02 2278401300055 2.7973 0.63333 4.0665E-02 2278401300056 2.8549 0.63321 2.5092E-02 2278401300057 2.9124 0.61369 4.9644E-02 2278401300058 2.9505 0.58109 4.2140E-02 2278401300059 2.9888 0.56322 4.2134E-02 2278401300060 3.0462 0.53743 3.8974E-02 2278401300061 3.1327 0.53727 3.0066E-02 2278401300062 3.1805 0.52073 4.6408E-02 2278401300063 3.2469 0.43872 3.1800E-02 2278401300064 3.3042 0.40898 4.5042E-02 2278401300065 3.3712 0.39636 3.8110E-02 2278401300066 3.4385 0.39936 4.2469E-02 2278401300067 3.5057 0.39618 2.8730E-02 2278401300068 3.5436 0.3525 2.5563E-02 2278401300069 3.5817 0.33638 2.0295E-02 2278401300070 3.6489 0.33112 2.9580E-02 2278401300071 3.6968 0.32343 1.8099E-02 2278401300072 3.7542 0.30862 2.4965E-02 2278401300073 3.8022 0.3038 1.7001E-02 2278401300074 3.8692 0.28988 1.8623E-02 2278401300075 3.9267 0.28535 2.3083E-02 2278401300076 3.9939 0.28529 2.3068E-02 2278401300077 4.061 0.27434 1.9885E-02 2278401300078 4.0702 0.25184 1.8847E-02 2278401300079 4.1373 0.24597 1.7829E-02 2278401300080 4.1852 0.24214 1.6379E-02 2278401300081 4.2331 0.23468 1.8976E-02 2278401300082 4.2812 0.23647 1.7698E-02 2278401300083 4.3484 0.23827 1.9266E-02 2278401300084 4.377 0.22562 1.6354E-02 2278401300085 4.4435 0.19457 1.5740E-02 2278401300086 4.4716 0.17179 1.7725E-02 2278401300087 4.5387 0.16649 1.4867E-02 2278401300088 4.5673 0.16012 1.4270E-02 2278401300089 4.6345 0.15884 1.1519E-02 2278401300090 4.6822 0.14923 1.2238E-02 2278401300091 4.7495 0.1492 9.5850E-03 2278401300092 4.778 0.14128 1.0569E-02 2278401300093 4.8258 0.13377 9.6961E-03 2278401300094 4.864 0.12865 9.6282E-03 2278401300095 4.9212 0.11716 1.0445E-02 2278401300096 4.9504 0.12762 1.0323E-02 2278401300097 5.0178 0.13162 1.4002E-02 2278401300098 5.0946 0.13057 7.3067E-03 2278401300099 5.1329 0.12754 1.1389E-02 2278401300100 5.1519 0.12171 8.8223E-03 2278401300101 5.1806 0.1189 8.0355E-03 2278401300102 5.2091 0.11258 9.1033E-03 2278401300103 5.2467 9.5604E-02 7.7337E-03 2278401300104 5.2936 7.6284E-02 8.7768E-03 2278401300105 5.3508 7.0015E-02 1.0548E-02 2278401300106 5.3799 7.3925E-02 8.6555E-03 2278401300107 5.4474 7.7440E-02 5.6131E-03 2278401300108 5.5053 8.2396E-02 8.7681E-03 2278401300109 5.592 8.6982E-02 1.0008E-02 2278401300110 5.6303 8.4306E-02 9.7028E-03 2278401300111 5.6587 7.7385E-02 5.6064E-03 2278401300112 5.6969 7.4423E-02 9.2187E-03 2278401300113 5.7441 6.3690E-02 7.3255E-03 2278401300114 5.7822 5.9839E-02 6.3656E-03 2278401300115 5.8203 5.6222E-02 5.4988E-03 2278401300116 5.8582 5.0023E-02 4.0448E-03 2278401300117 5.9152 4.4506E-02 3.6498E-03 2278401300118 5.9336 3.8091E-02 2.8496E-03 2278401300119 5.9526 3.6635E-02 9.7954E-03 2278401300120 5.9914 3.8983E-02 4.8232E-03 2278401300121 6.0098 3.3364E-02 6.9433E-03 2278401300122 6.0496 4.3459E-02 5.7600E-03 2278401300123 6.1076 4.6966E-02 7.9058E-03 2278401300124 6.1841 4.3779E-02 4.5159E-03 2278401300125 6.1929 3.7180E-02 7.0432E-03 2278401300126 6.2498 3.2822E-02 6.6285E-03 2278401300127 6.3082 3.7748E-02 7.3870E-03 2278401300128 6.3187 4.5142E-02 5.2828E-03 2278401300129 6.3477 4.6564E-02 6.5833E-03 2278401300130 6.4344 4.8774E-02 1.0933E-02 2278401300131 6.4823 4.7273E-02 6.6835E-03 2278401300132 6.5293 3.9216E-02 5.8924E-03 2278401300133 6.5948 2.7843E-02 6.1355E-03 2278401300134 6.6496 1.5900E-02 6.0078E-03 2278401300135 6.6929 6.3983E-03 4.2098E-03 2278401300136 6.9494 3.6513E-03 2.0627E-03 2278401300137 6.9946 1.3593E-02 4.0892E-03 2278401300138 7.0365 2.6741E-02 5.8919E-03 2278401300139 7.0862 3.7067E-02 6.5778E-03 2278401300140 7.1248 3.7938E-02 6.7293E-03 2278401300141 7.1907 2.9802E-02 4.4780E-03 2278401300142 7.236 1.7286E-02 3.1657E-03 2278401300143 7.2987 7.2315E-03 3.9477E-03 2278401300144 ENDDATA 126 0 2278401300145 ENDSUBENT 144 0 2278401399999 SUBENT 22784014 20081124 22062278401400001 BIB 5 9 2278401400002 REACTION (60-ND-145(N,G)60-ND-146,,MLT/DE,,SPA) Averaged 2278401400003 over neutron energy interval 2278401400004 EN-SEC (E,G) E-RSL is gamma ray energy bin 2278401400005 ERR-ANALYS (E-ERR-DIG) Secongary gamma energy digitizing error 2278401400006 (ERR-DIG) Data digi9izing error 2278401400007 (DATA-ERR) Error from the graphic bars 2278401400008 STATUS (CURVE) Fig.10 of main reference (Nd-145, 550 keV) 2278401400009 (DEP,22784009) Sample, Inc-Source, Analysis 2278401400010 HISTORY (20081124C) SM 2278401400011 ENDBIB 9 0 2278401400012 COMMON 5 3 2278401400013 EN-MEAN EN-RSL E-RSL E-ERR-DIG ERR-DIG 2278401400014 KEV KEV KEV MEV PT/RCT/MEV 2278401400015 550. 100. 100. 8.8501E-03 1.6997E-03 2278401400016 ENDCOMMON 3 0 2278401400017 DATA 3 76 2278401400018 E DATA DATA-ERR 2278401400019 MEV PT/RCT/MEV PT/RCT/MEV 2278401400020 0.59116 1.6011 0.52503 2278401400021 0.699 2.4188 0.54843 2278401400022 0.7962 3.0075 0.41386 2278401400023 0.89038 2.1009 0.33102 2278401400024 0.99433 1.514 0.30616 2278401400025 1.0992 1.295 0.33192 2278401400026 1.205 1.3355 0.28656 2278401400027 1.2917 1.399 0.24767 2278401400028 1.3875 1.3347 0.21022 2278401400029 1.4839 1.409 0.2494 2278401400030 1.5991 1.3867 0.20939 2278401400031 1.6948 1.3025 0.17927 2278401400032 1.8 1.1951 0.16445 2278401400033 1.886 1.0966 0.1435 2278401400034 2.0013 1.1047 0.12955 2278401400035 2.097 1.0295 0.13473 2278401400036 2.1929 1.0054 0.11788 2278401400037 2.3081 0.97418 0.15548 2278401400038 2.4037 0.89386 0.11079 2278401400039 2.499 0.78271 9.7105E-02 2278401400040 2.5854 0.77037 9.0319E-02 2278401400041 2.7007 0.77007 9.5537E-02 2278401400042 2.7961 0.67958 9.0231E-02 2278401400043 2.9007 0.55475 8.3752E-02 2278401400044 2.9866 0.50508 7.9581E-02 2278401400045 3.0826 0.49325 7.8686E-02 2278401400046 3.188 0.47055 7.4127E-02 2278401400047 3.2933 0.43511 7.1390E-02 2278401400048 3.3986 0.40867 7.2334E-02 2278401400049 3.4944 0.38988 7.3969E-02 2278401400050 3.5899 0.3522 6.9115E-02 2278401400051 3.6951 0.32315 6.3427E-02 2278401400052 3.791 0.30829 5.6553E-02 2278401400053 3.906 0.29409 5.5804E-02 2278401400054 4.0014 0.26156 5.1270E-02 2278401400055 4.0971 0.24188 5.0418E-02 2278401400056 4.2028 0.24368 5.0794E-02 2278401400057 4.2986 0.23067 5.0905E-02 2278401400058 4.4035 0.20198 4.9242E-02 2278401400059 4.4986 0.16617 4.9147E-02 2278401400060 4.6034 0.14214 4.4352E-02 2278401400061 4.6996 0.14545 4.6166E-02 2278401400062 4.795 0.12836 4.4746E-02 2278401400063 4.8997 0.10643 4.7101E-02 2278401400064 5.0152 0.11235 4.8241E-02 2278401400065 5.1026 0.13229 4.5437E-02 2278401400066 5.1985 0.12818 4.0000E-02 2278401400067 5.3036 0.1167 3.7655E-02 2278401400068 5.3898 0.11134 3.7091E-02 2278401400069 5.504 9.0882E-02 3.7380E-02 2278401400070 5.5981 6.2503E-02 3.4924E-02 2278401400071 5.7027 5.0234E-02 3.4130E-02 2278401400072 5.7896 5.5141E-02 3.6618E-02 2278401400073 5.9049 5.5550E-02 4.0430E-02 2278401400074 6.0016 6.2416E-02 4.1285E-02 2278401400075 6.099 8.1322E-02 3.8730E-02 2278401400076 6.1954 8.5852E-02 3.2480E-02 2278401400077 6.2896 6.0441E-02 3.1158E-02 2278401400078 6.403 4.2548E-02 4.1464E-02 2278401400079 6.5001 5.1280E-02 3.5346E-02 2278401400080 6.6072 6.7333E-02 3.1513E-02 2278401400081 6.7025 5.8960E-02 3.9762E-02 2278401400082 6.797 4.3157E-02 4.1969E-02 2278401400083 6.894 5.2421E-02 3.6755E-02 2278401400084 6.9921 7.7368E-02 4.1595E-02 2278401400085 7.0976 7.3808E-02 3.4543E-02 2278401400086 7.2009 4.6954E-02 3.0682E-02 2278401400087 7.3054 3.7737E-02 2.1471E-02 2278401400088 7.402 4.1746E-02 2.9169E-02 2278401400089 7.4986 4.6542E-02 4.1721E-02 2278401400090 7.5952 5.1086E-02 4.7745E-02 2278401400091 7.7013 5.6073E-02 5.5019E-02 2278401400092 7.8068 5.4332E-02 3.2498E-02 2278401400093 7.8831 4.8704E-02 2.0034E-02 2278401400094 7.9975 4.1660E-02 1.2775E-02 2278401400095 8.1012 2.8428E-02 7.6124E-03 2278401400096 ENDDATA 78 0 2278401400097 ENDSUBENT 96 0 2278401499999 SUBENT 22784015 20081124 22062278401500001 BIB 5 9 2278401500002 REACTION (60-ND-146(N,G)60-ND-147,,MLT/DE,,SPA) Averaged 2278401500003 over neutron energy interval 2278401500004 EN-SEC (E,G) E-RSL is gamma ray energy bin 2278401500005 ERR-ANALYS (E-ERR-DIG) Secongary gamma energy digitizing error 2278401500006 (ERR-DIG) Data digi9izing error 2278401500007 (DATA-ERR) Error from the graphic bars 2278401500008 STATUS (CURVE) Fig.10 of main reference (Nd-146, 35-90keV) 2278401500009 (DEP,22784004) Sample, N-Source, Analysis 2278401500010 HISTORY (20081124C) SM 2278401500011 ENDBIB 9 0 2278401500012 COMMON 5 3 2278401500013 EN-MIN EN-MAX E-RSL E-ERR-DIG ERR-DIG 2278401500014 KEV KEV KEV MEV PT/RCT/MEV 2278401500015 35. 90. 50. 7.9873E-03 3.5079E-03 2278401500016 ENDCOMMON 3 0 2278401500017 DATA 3 88 2278401500018 E DATA DATA-ERR 2278401500019 MEV PT/RCT/MEV PT/RCT/MEV 2278401500020 0.62681 1.1259 0.20953 2278401500021 0.69443 0.93365 0.19249 2278401500022 0.71376 1.1761 0.13981 2278401500023 0.77173 1.0644 0.13398 2278401500024 0.84902 0.96927 0.14 2278401500025 0.90699 0.92784 0.12333 2278401500026 0.94563 0.87171 0.13453 2278401500027 0.98427 0.7791 0.11253 2278401500028 1.0229 0.73655 0.13332 2278401500029 1.0809 0.76464 0.11045 2278401500030 1.0906 0.85554 0.10769 2278401500031 1.1292 0.89933 0.19877 2278401500032 1.1678 0.79381 0.14773 2278401500033 1.1775 0.75516 0.14816 2278401500034 1.2065 0.81388 0.12189 2278401500035 1.2548 0.89933 0.10055 2278401500036 1.3611 0.95128 0.1606 2278401500037 1.4287 0.94536 0.15273 2278401500038 1.477 0.77909 0.13703 2278401500039 1.5446 0.75515 0.14436 2278401500040 1.5833 0.83966 0.12128 2278401500041 1.6606 0.95723 0.11379 2278401500042 1.7379 0.79381 0.11041 2278401500043 1.7765 0.85021 0.10442 2278401500044 1.8345 0.92205 0.10319 2278401500045 1.9118 0.86627 7.2466E-02 2278401500046 1.9601 0.82409 8.7553E-02 2278401500047 2.0471 0.87169 7.7889E-02 2278401500048 2.0954 0.91061 7.0805E-02 2278401500049 2.163 0.87169 8.2827E-02 2278401500050 2.25 0.88816 9.9396E-02 2278401500051 2.2886 0.80377 9.5545E-02 2278401500052 2.3466 0.75514 6.3811E-02 2278401500053 2.3852 0.70066 6.2607E-02 2278401500054 2.4625 0.63805 6.4219E-02 2278401500055 2.5591 0.68766 7.6958E-02 2278401500056 2.6267 0.60698 5.5412E-02 2278401500057 2.6944 0.55969 5.9462E-02 2278401500058 2.7523 0.57383 4.8490E-02 2278401500059 2.8393 0.51608 5.4829E-02 2278401500060 2.8876 0.50967 3.6213E-02 2278401500061 2.9166 0.47884 4.5499E-02 2278401500062 2.9552 0.49402 3.8413E-02 2278401500063 3.0518 0.45552 3.8493E-02 2278401500064 3.0615 0.43878 3.4118E-02 2278401500065 3.1002 0.42003 2.7045E-02 2278401500066 3.1678 0.39709 2.0326E-02 2278401500067 3.1968 0.38012 3.1798E-02 2278401500068 3.303 0.36615 4.8670E-02 2278401500069 3.3417 0.35269 2.9504E-02 2278401500070 3.4093 0.32118 2.7140E-02 2278401500071 3.4576 0.29248 3.0709E-02 2278401500072 3.5252 0.28527 2.8712E-02 2278401500073 3.5736 0.25816 2.8863E-02 2278401500074 3.6219 0.26634 3.1661E-02 2278401500075 3.7088 0.24713 2.7657E-02 2278401500076 3.7378 0.21143 2.0746E-02 2278401500077 3.7958 0.18897 1.9019E-02 2278401500078 3.8441 0.17754 1.4852E-02 2278401500079 3.8731 0.19254 2.4236E-02 2278401500080 3.931 0.15867 1.4178E-02 2278401500081 3.9793 0.1454 1.7060E-02 2278401500082 4.0083 0.16473 1.5038E-02 2278401500083 4.0566 0.15573 1.9977E-02 2278401500084 4.0953 0.19134 2.5434E-02 2278401500085 4.1629 0.20622 2.7411E-02 2278401500086 4.2112 0.19374 2.3031E-02 2278401500087 4.2402 0.16268 2.0478E-02 2278401500088 4.2788 0.13407 1.7821E-02 2278401500089 4.3561 0.10643 2.1413E-02 2278401500090 4.4141 0.12286 1.9049E-02 2278401500091 4.5204 0.12995 2.8721E-02 2278401500092 4.5204 0.12362 2.1776E-02 2278401500093 4.6073 0.11834 1.9589E-02 2278401500094 4.617 0.12518 2.0721E-02 2278401500095 4.6943 0.12754 1.6054E-02 2278401500096 4.7522 0.1366 1.8158E-02 2278401500097 4.7909 0.13407 2.4603E-02 2278401500098 4.8392 0.12995 2.0056E-02 2278401500099 4.8972 0.11328 1.6966E-02 2278401500100 4.9455 0.11908 2.3363E-02 2278401500101 5.0034 0.12675 1.8982E-02 2278401500102 5.0807 0.1454 1.7284E-02 2278401500103 5.1291 0.15094 2.4386E-02 2278401500104 5.1967 0.14449 1.9207E-02 2278401500105 5.2546 0.11188 1.7266E-02 2278401500106 5.3029 6.6236E-02 1.4136E-02 2278401500107 5.3319 2.7307E-02 7.5667E-03 2278401500108 ENDDATA 90 0 2278401500109 ENDSUBENT 108 0 2278401599999 SUBENT 22784016 20081124 22062278401600001 BIB 5 9 2278401600002 REACTION (60-ND-146(N,G)60-ND-147,,MLT/DE,,SPA) Averaged 2278401600003 over neutron energy interval 2278401600004 EN-SEC (E,G) E-RSL is gamma ray energy bin 2278401600005 ERR-ANALYS (E-ERR-DIG) Secongary gamma energy digitizing error 2278401600006 (ERR-DIG) Data digi9izing error 2278401600007 (DATA-ERR) Error from the graphic bars 2278401600008 STATUS (CURVE) Fig.10 of main reference (Nd-146, 550 keV) 2278401600009 (DEP,22784010) Sample, N-Source, Analysis 2278401600010 HISTORY (20081124C) SM 2278401600011 ENDBIB 9 0 2278401600012 COMMON 5 3 2278401600013 EN-MEAN EN-RSL E-RSL E-ERR-DIG ERR-DIG 2278401600014 KEV KEV KEV MEV PT/RCT/MEV 2278401600015 550. 70. 100. 3.3243E-03 1.4664E-03 2278401600016 ENDCOMMON 3 0 2278401600017 DATA 3 54 2278401600018 E DATA DATA-ERR 2278401600019 MEV PT/RCT/MEV PT/RCT/MEV 2278401600020 0.58464 1.0293 0.24195 2278401600021 0.69081 0.89185 0.25484 2278401600022 0.78764 1.2028 0.25361 2278401600023 0.8938 1.0165 0.24376 2278401600024 0.99043 1.0356 0.23849 2278401600025 1.087 0.91997 0.24208 2278401600026 1.1933 1.0164 0.21929 2278401600027 1.2996 1.0227 0.17439 2278401600028 1.3866 1.1512 0.1963 2278401600029 1.4736 1.0884 0.1628 2278401600030 1.5895 1.0226 0.11983 2278401600031 1.6861 1.0226 0.11983 2278401600032 1.7924 1.0226 0.11418 2278401600033 1.8792 0.93712 0.10464 2278401600034 1.9952 0.89151 9.4595E-02 2278401600035 2.0918 0.94881 9.9479E-02 2278401600036 2.2077 0.88042 0.10451 2278401600037 2.2945 0.72123 8.8470E-02 2278401600038 2.4009 0.88587 5.8692E-02 2278401600039 2.4975 0.76279 7.2386E-02 2278401600040 2.5843 0.61713 6.8966E-02 2278401600041 2.6905 0.57623 6.0415E-02 2278401600042 2.787 0.52807 6.4775E-02 2278401600043 2.8837 0.56906 5.1878E-02 2278401600044 2.9899 0.5055 5.6444E-02 2278401600045 3.0865 0.46907 5.2419E-02 2278401600046 3.183 0.4039 4.7943E-02 2278401600047 3.2795 0.33922 4.8936E-02 2278401600048 3.3857 0.29946 4.8310E-02 2278401600049 3.4822 0.26272 5.1483E-02 2278401600050 3.5788 0.24838 4.7425E-02 2278401600051 3.6947 0.24076 4.0587E-02 2278401600052 3.7816 0.21254 4.1649E-02 2278401600053 3.8878 0.19236 3.8656E-02 2278401600054 3.9746 0.15466 3.7821E-02 2278401600055 4.0809 0.1741 3.7563E-02 2278401600056 4.1873 0.18761 3.5822E-02 2278401600057 4.2838 0.17409 3.5787E-02 2278401600058 4.3804 0.16255 3.5071E-02 2278401600059 4.4866 0.14084 3.5102E-02 2278401600060 4.5928 0.13483 3.2333E-02 2278401600061 4.6893 0.11394 3.3566E-02 2278401600062 4.7956 0.11394 3.3565E-02 2278401600063 4.8828 0.15559 3.7312E-02 2278401600064 4.9987 0.15754 3.3989E-02 2278401600065 5.0953 0.14082 3.1749E-02 2278401600066 5.1919 0.13564 2.7931E-02 2278401600067 5.2884 0.12354 2.7853E-02 2278401600068 5.3753 0.10571 2.6347E-02 2278401600069 5.491 7.9859E-02 2.5593E-02 2278401600070 5.5877 9.2739E-02 2.5668E-02 2278401600071 5.6942 0.1132 2.4424E-02 2278401600072 5.7808 7.7402E-02 5.3861E-02 2278401600073 5.9056 2.2819E-02 1.2348E-02 2278401600074 ENDDATA 56 0 2278401600075 ENDSUBENT 74 0 2278401699999 ENDENTRY 16 0 2278499999999