ENTRY 10856 20200229 14641085600000001 SUBENT 10856001 20200229 14641085600100001 BIB 13 25 1085600100002 INSTITUTE (1USABRN) 1085600100003 REFERENCE (J,BAP,23,525(BI1),1978) 1085600100004 (W,MAXSON,197903) Tabulated data 1085600100005 AUTHOR (J.Bading,D.R.Maxson) 1085600100006 TITLE Excitation function and angular distribution studies 1085600100007 of N-15(n,deuteron)C-14-g and N-15(n,triton)C-13-g 1085600100008 with neutron energies from 13.6 to 14.8-MeV. 1085600100009 INC-SOURCE (D-T) 1085600100010 SAMPLE N-15 enriched melamine targets (N(6)C(3)H(6)). 1085600100011 Sample thicknesses - 5.04,2.85 and 2.08 mg/cm**2. 1085600100012 METHOD Vacuum evaporation, differential weighing, mass 1085600100013 spectroscopy to determine N isotopic composition. 1085600100014 DETECTOR (TELES) Telescope consisting of two differential gas 1085600100015 counters and a cesium-iodide scintillator 1085600100016 (SOLST) Silicon detector used for neutron spectra 1085600100017 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 1085600100018 CORRECTION Corrected for contributions to range of 1085600100019 N-15(n,d0)C-14 group in multichannel analyzer spectrum1085600100020 from N-14(n,d) and N-14(n,t) reactions in N-14 1085600100021 contaminent of reactor targets. 1085600100022 ERR-ANALYS (DATA-ERR) Errors stated as one standard deviation. 1085600100023 STATUS (TABLE) Data from Maxson, March 1979 1085600100024 HISTORY (19790502C) 1085600100025 (20200124U) OS. STATUS added, converted to lower case, 1085600100026 minor BIB changes. 1085600100027 ENDBIB 25 0 1085600100028 COMMON 2 3 1085600100029 E-LVL EN-NRM 1085600100030 KEV MEV 1085600100031 0. 14.1 1085600100032 ENDCOMMON 3 0 1085600100033 ENDSUBENT 32 0 1085600199999 SUBENT 10856002 19790608 00001085600200001 BIB 1 1 1085600200002 REACTION (7-N-15(N,D)6-C-14,PAR,DA) 1085600200003 ENDBIB 1 0 1085600200004 NOCOMMON 0 0 1085600200005 DATA 6 13 1085600200006 EN EN-ERR EN-RSL ANG DATA DATA-ERR 1085600200007 MEV MEV KEV ADEG MB/SR MB/SR 1085600200008 13.59 0.02 122. 0. 2.97 0.52 1085600200009 13.59 0.02 122. 45. 1.29 0.23 1085600200010 13.84 0.03 119. 0. 2.44 0.48 1085600200011 13.84 0.03 139. 45. 1.65 0.41 1085600200012 14.08 0.03 111. 0. 2.64 0.40 1085600200013 14.10 0.03 118. 45. 1.13 0.32 1085600200014 14.37 0.03 173. 0. 2.68 0.56 1085600200015 14.37 0.03 173. 45. 1.05 0.33 1085600200016 14.55 0.03 230. 0. 2.96 0.65 1085600200017 14.55 0.03 230. 45. 1.21 0.44 1085600200018 14.73 0.02 183. 0. 3.28 0.51 1085600200019 14.80 0.03 330. 0. 1.89 0.41 1085600200020 14.80 0.03 330. 45. 1.12 0.30 1085600200021 ENDDATA 15 0 1085600200022 ENDSUBENT 21 0 1085600299999 SUBENT 10856003 19790608 00001085600300001 BIB 1 1 1085600300002 REACTION (7-N-15(N,T)6-C-13,PAR,DA) 1085600300003 ENDBIB 1 0 1085600300004 NOCOMMON 0 0 1085600300005 DATA 6 12 1085600300006 EN EN-ERR EN-RSL ANG DATA DATA-ERR 1085600300007 MEV MEV KEV ADEG MB/SR MB/SR 1085600300008 13.59 0.02 122. 0. 1.52 0.52 1085600300009 13.84 0.03 119. 0. 2.15 0.44 1085600300010 13.84 0.03 139. 45. 1.06 0.60 1085600300011 14.08 0.03 111. 0. 2.30 0.35 1085600300012 14.10 0.03 118. 45. 1.31 0.33 1085600300013 14.37 0.03 173. 0. 3.70 0.59 1085600300014 14.37 0.03 173. 45. 1.32 0.31 1085600300015 14.55 0.03 230. 0. 3.72 0.58 1085600300016 14.55 0.03 230. 45. 1.74 0.38 1085600300017 14.73 0.02 183. 0. 2.77 0.64 1085600300018 14.80 0.03 330. 0. 3.60 0.50 1085600300019 14.80 0.03 330. 45. 0.94 0.24 1085600300020 ENDDATA 14 0 1085600300021 ENDSUBENT 20 0 1085600399999 SUBENT 10856004 20200229 14641085600400001 BIB 2 3 1085600400002 REACTION (7-N-15(N,D)6-C-14,PAR,DA) 1085600400003 INC-SPECT 14.08-MeV neutron energy varies between 14.07 and 1085600400004 14.10-MeV among the data points 1085600400005 ENDBIB 3 0 1085600400006 NOCOMMON 0 0 1085600400007 DATA 6 21 1085600400008 EN EN-ERR EN-RSL ANG-CM DATA-CM DATA-ERR 1085600400009 MEV MEV KEV ADEG MB/SR MB/SR 1085600400010 14.08 120. 7.0 1.98 0.30 1085600400011 14.08 120. 9.5 1.71 0.29 1085600400012 14.08 120. 11.1 2.29 0.39 1085600400013 14.08 120. 14.7 2.58 0.47 1085600400014 14.08 120. 20.0 2.94 0.51 1085600400015 14.08 120. 34.8 1.88 0.38 1085600400016 14.08 120. 43.2 1.02 0.26 1085600400017 14.08 120. 51.6 0.92 0.26 1085600400018 14.08 120. 67.8 0.87 0.21 1085600400019 14.08 120. 88.9 0.35 0.20 1085600400020 14.08 120. 109. -0.35 0.45 1085600400021 14.55 0.03 240. 8.2 2.22 0.49 1085600400022 14.55 0.03 240. 51.4 1.01 0.36 1085600400023 14.57 0.02 240. 13.3 2.16 0.36 1085600400024 14.57 0.02 240. 18.3 3.26 0.48 1085600400025 14.57 0.02 240. 25.9 2.74 0.40 1085600400026 14.57 0.02 240. 37.5 1.42 0.33 1085600400027 14.57 0.02 240. 43.1 0.84 0.22 1085600400028 14.57 0.02 240. 67.7 1.20 0.37 1085600400029 14.57 0.02 240. 88.8 0.28 0.19 1085600400030 14.57 0.02 240. 108.7 0.015 0.37 1085600400031 ENDDATA 23 0 1085600400032 ENDSUBENT 31 0 1085600499999 SUBENT 10856005 20200229 14641085600500001 BIB 2 3 1085600500002 REACTION (7-N-15(N,T)6-C-13,PAR,DA) 1085600500003 INC-SPECT 14.08-MeV neutron energy varies between 14.07 and 1085600500004 14.10-MeV among the data points 1085600500005 ENDBIB 3 0 1085600500006 NOCOMMON 0 0 1085600500007 DATA 6 13 1085600500008 EN EN-ERR EN-RSL ANG-CM DATA-CM DATA-ERR 1085600500009 MEV MEV KEV ADEG MB/SR MB/SR 1085600500010 14.08 120. 7.6 1.48 0.22 1085600500011 14.08 120. 12.0 1.51 0.29 1085600500012 14.08 120. 16.0 1.47 0.29 1085600500013 14.08 120. 22.7 1.01 0.28 1085600500014 14.08 120. 37.5 1.68 0.33 1085600500015 14.08 120. 55.4 0.96 0.24 1085600500016 14.55 0.03 240. 8.8 2.43 0.39 1085600500017 14.55 0.03 240. 55.0 1.43 0.28 1085600500018 14.57 0.02 240. 14.2 2.28 0.33 1085600500019 14.57 0.02 240. 19.6 2.13 0.33 1085600500020 14.57 0.02 240. 27.7 2.17 0.30 1085600500021 14.57 0.02 240. 40.2 1.79 0.29 1085600500022 14.57 0.02 240. 72.0 0.97 0.37 1085600500023 ENDDATA 15 0 1085600500024 ENDSUBENT 23 0 1085600599999 ENDENTRY 5 0 1085699999999