ENTRY 41446 20111215 41554144600000001 SUBENT 41446001 20111215 41554144600100001 BIB 12 26 4144600100002 TITLE Neutron Emission from the Reaction 232-Th(N,XN'F). 4144600100003 AUTHOR (G.N.Lovchikova,A.M.Trufanov,M.I.Svirin,V.A.Vinogradov)4144600100004 INSTITUTE (4RUSFEI) 4144600100005 REFERENCE (J,YF,67,(5),914,200405) 4144600100006 (J,PAN,67,(5),890,2004) Engl. translation of J,YF. 4144600100007 #doi:10.1134/1.1755381 4144600100008 FACILITY (VDG,4RUSFEI) KG-2.5 4144600100009 METHOD (TOF) 1.7 m flight at 90 degrees to neutron beam 4144600100010 INC-SOURCE (D-T) Solid T-Ti-target 4144600100011 DETECTOR (IOCH) Four-sections ionization chamber 4144600100012 (SCIN) Stilbene crystal of 63 mm diameter, 39mm height,4144600100013 threshold energy 250 keV. 4144600100014 SAMPLE Three ionization chamber section: 4144600100015 232-Th 12 layers of 2 mg/cm**2 thickness and 100mm 4144600100016 diameter on two sides of aluminum foil. 4144600100017 Total 232-Th weight 5.65 g. 4144600100018 In 4th section - 2 one-side Th-232 layers 4144600100019 with 252-Cf nucleus. 4144600100020 MONITOR (98-CF-252(0,F),PR,NU/DE) 4144600100021 ERR-ANALYS (DATA-ERR) Total error 4144600100022 HISTORY (20050412C) Compiled at CJD (M.M) 4144600100023 (20050422U) Last checking has been done. 4144600100024 (20060202A) Sub.004 was added.(M.M.) 4144600100025 (20100225U) Ref. J,PAN was added. 4144600100026 ERR-T -> DATA-ERR. TABLE was added in STATUS . 4144600100027 (20111215A) Subent 004 reaction was corrected. 4144600100028 ENDBIB 26 0 4144600100029 NOCOMMON 0 0 4144600100030 ENDSUBENT 29 0 4144600199999 SUBENT 41446002 20111215 41554144600200001 BIB 2 2 4144600200002 REACTION (90-TH-232(N,F)0-NN-1,PR,KE) 4144600200003 STATUS (TABLE) From Table 2 of J,YF,67,(5),914,2004 4144600200004 ENDBIB 2 0 4144600200005 NOCOMMON 0 0 4144600200006 DATA 3 2 4144600200007 EN DATA DATA-ERR 4144600200008 MEV MEV MEV 4144600200009 14.9 1.87 0.04 4144600200010 17.7 1.95 0.04 4144600200011 ENDDATA 4 0 4144600200012 ENDSUBENT 11 0 4144600299999 SUBENT 41446003 20111215 41554144600300001 BIB 2 2 4144600300002 REACTION (90-TH-232(N,F),PR,NU) 4144600300003 STATUS (TABLE) From Table 2 of J,YF,67,(5),914,2004 4144600300004 ENDBIB 2 0 4144600300005 NOCOMMON 0 0 4144600300006 DATA 3 2 4144600300007 EN DATA DATA-ERR 4144600300008 MEV PRT/FIS PRT/FIS 4144600300009 14.9 4.06 0.1 4144600300010 17.7 4.33 0.13 4144600300011 ENDDATA 4 0 4144600300012 ENDSUBENT 11 0 4144600399999 SUBENT 41446004 20111215 41554144600400001 BIB 4 12 4144600400002 REACTION ((90-TH-232(N,F),PR,NU/DE,,NPD)/ 4144600400003 (98-CF-252(0,F),PR,NU/DE,,NPD)) 4144600400004 Experimental ratio of normalized to 1.0 neutron 4144600400005 spectra 4144600400006 EN-SEC (E,N) Energy of fission neutrons 4144600400007 STATUS (APRVD) Data received from author M.Svirin 20060131. 4144600400008 Fig.1 of reference. 4144600400009 (TABLE) From author. 4144600400010 HISTORY (20111215A) 4144600400011 (90-TH-232(N,F),PR,DE,N)/(98-CF-252(0,F),PR,DE,N) -> 4144600400012 (90-TH-232(N,F),PR,NU/DE,,NPD)/ 4144600400013 (98-CF-252(0,F),PR,NU/DE,,NPD) . 4144600400014 ENDBIB 12 0 4144600400015 NOCOMMON 0 0 4144600400016 DATA 4 66 4144600400017 EN E DATA DATA-ERR 4144600400018 MEV MEV NO-DIM PER-CENT 4144600400019 14.6 0.40 1.444 5.3 4144600400020 14.6 0.59 1.289 2.7 4144600400021 14.6 0.79 1.268 3. 4144600400022 14.6 0.99 1.174 2.7 4144600400023 14.6 1.20 1.152 2.4 4144600400024 14.6 1.40 0.981 2.4 4144600400025 14.6 1.60 0.925 2.6 4144600400026 14.6 1.80 0.877 2.7 4144600400027 14.6 2. 0.868 2.8 4144600400028 14.6 2.20 0.905 3.1 4144600400029 14.6 2.40 0.816 3.3 4144600400030 14.6 2.59 0.827 3.7 4144600400031 14.6 2.79 0.775 3.6 4144600400032 14.6 3.00 0.812 4.2 4144600400033 14.6 3.30 0.789 3.1 4144600400034 14.6 3.69 0.801 3.6 4144600400035 14.6 4.10 0.823 4.3 4144600400036 14.6 4.51 0.759 5. 4144600400037 14.6 4.90 0.717 5.8 4144600400038 14.6 5.30 0.849 7.6 4144600400039 14.6 5.69 0.799 8.1 4144600400040 14.6 6.07 0.94 10. 4144600400041 14.6 6.62 0.775 8.9 4144600400042 14.6 7.32 0.917 12. 4144600400043 14.6 7.97 1.566 17. 4144600400044 14.6 8.71 1.211 24. 4144600400045 14.6 9.44 0.976 45. 4144600400046 14.6 10.14 0.888 84. 4144600400047 17.7 0.55 1.103 7.4 4144600400048 17.7 0.7 1.192 7. 4144600400049 17.7 0.85 1.171 4.7 4144600400050 17.7 1. 1.093 3.5 4144600400051 17.7 1.15 1.095 3.6 4144600400052 17.7 1.3 1.087 3.6 4144600400053 17.7 1.45 1.04 3.3 4144600400054 17.7 1.6 1.016 3.4 4144600400055 17.7 1.75 0.982 3.5 4144600400056 17.7 1.9 1.012 3.8 4144600400057 17.7 2.05 0.957 3.3 4144600400058 17.7 2.2 0.94 2.7 4144600400059 17.7 2.35 0.939 2.7 4144600400060 17.7 2.5 0.908 2.6 4144600400061 17.7 2.65 0.909 2.7 4144600400062 17.7 2.8 0.887 2.6 4144600400063 17.7 2.95 0.843 2.7 4144600400064 17.7 3.1 0.887 5.4 4144600400065 17.7 3.25 0.879 5.1 4144600400066 17.7 3.4 0.855 4.5 4144600400067 17.7 3.55 0.822 4. 4144600400068 17.7 3.7 0.846 4.6 4144600400069 17.7 3.85 0.832 5.4 4144600400070 17.7 4.0 0.889 4.9 4144600400071 17.7 4.3 0.839 3.1 4144600400072 17.7 4.75 0.816 3.9 4144600400073 17.7 5.28 0.815 4.3 4144600400074 17.7 5.8 0.764 6.1 4144600400075 17.7 6.33 0.837 5.7 4144600400076 17.7 6.85 0.862 8.3 4144600400077 17.7 7.3 0.833 8.7 4144600400078 17.7 7.9 0.965 10.5 4144600400079 17.7 8.65 1.009 10.3 4144600400080 17.7 9.7 1.246 13.2 4144600400081 17.7 10.83 1.483 18. 4144600400082 17.7 11.88 1.847 19. 4144600400083 17.7 12.78 1.926 17. 4144600400084 17.7 13.75 1.438 43. 4144600400085 ENDDATA 68 0 4144600400086 ENDSUBENT 85 0 4144600499999 ENDENTRY 4 0 4144699999999