ENTRY 13811 20050722 13361381100000001 SUBENT 13811001 20050722 13361381100100001 BIB 16 40 1381100100002 INSTITUTE (1USAANL) 1381100100003 REFERENCE (J,NIM,56,325,1967) 1381100100004 AUTHOR (G.E.Thomas, D.E.Blatchley, L.M.Bollinger) 1381100100005 TITLE High-Sensitivity Neutron-Capture Gamma-Ray Facility 1381100100006 FACILITY (REAC) Reactor CP-5. 1381100100007 INC-SOURCE (REAC) Reactor core. 1381100100008 INC-SPECT Reactor spectrum with cadmium ratio 7. 1381100100009 SAMPLE Samples of N, C, B, Li; (natural or enriched); 1381100100010 differing in size from a few mg to many g and placed 1381100100011 in the center of a 10.6-cm dia. aluminum tube that 1381100100012 passes through the reactor core. 1381100100013 METHOD Internal-target arrangement used so that the sample 1381100100014 (capture-gamma-ray source) was located in the 1381100100015 high-flux region of a reactor and was viewed (through 1381100100016 a collimator) by a detector located outside of the 1381100100017 reactor. 1381100100018 DETECTOR (GELI) Ge(Li) detector having a resolution width of 1381100100019 6.7 keV for 7-MeV gamma rays. The neutron flux on the 1381100100020 detector was reduced by collimators with neutron 1381100100021 absorbing and scattering materials (filters). 1381100100022 ANALYSIS The intensities were calculated from observed areas of 1381100100023 the gamma-ray lines, relative efficiencies established1381100100024 experimentally in advance, calculated gamma-ray 1381100100025 transmission of the neutron filter in the gamma-ray 1381100100026 beam and a normalizing factor that is a constant for 1381100100027 a given spectrum. 1381100100028 MONITOR The lines from capture in 12C present in the graphite 1381100100029 sample holder and 14N (when introduced in the tube) 1381100100030 were used as reference energy lines known with good 1381100100031 accuracy. 1381100100032 CORRECTION Correction of the observed gamma-ray-line areas for the1381100100033 background - mainly neutron-capture gamma rays emitted1381100100034 from structural components in the system. 1381100100035 ERR-ANALYS (DATA-ERR) Calculated by combining the statistical 1381100100036 error of the observed gamma-ray line area and the 1381100100037 systematic error of the relative efficiency. 1381100100038 (E-ERR) Estimated systematic uncertainty 1381100100039 STATUS Data taken from Tables 2, 3, 4, 5, 6 of reference 1381100100040 HISTORY (20010626C) IS 1381100100041 (20050722C) DR Reference corrected 1381100100042 ENDBIB 40 0 1381100100043 COMMON 1 3 1381100100044 EN-DUMMY 1381100100045 EV 1381100100046 0.0253 1381100100047 ENDCOMMON 3 0 1381100100048 ENDSUBENT 47 0 1381100199999 SUBENT 13811002 20010629 00001381100200001 BIB 2 2 1381100200002 REACTION (7-N-14(N,G)7-N-15,,SPC,,SPA) 1381100200003 SAMPLE Both nitrogen gas and Be(3)N(2) used as target material1381100200004 ENDBIB 2 0 1381100200005 NOCOMMON 0 0 1381100200006 DATA 4 23 1381100200007 E E-ERR DATA DATA-ERR 1381100200008 KEV KEV PC/REAC PC/REAC 1381100200009 10830. 2. 13.3 2.0 1381100200010 9151. 2. 1.7 0.2 1381100200011 9047. 4. 0.2 0.03 1381100200012 8570. 4. 0.2 0.03 1381100200013 8311. 2. 4.4 0.4 1381100200014 7299. 1. 10.0 0.5 1381100200015 6323. 1. 18.8 0.9 1381100200016 5562. 1. 10.3 0.5 1381100200017 5534. 1. 18.8 0.9 1381100200018 5298. 1. 21.4 1.1 1381100200019 5270. 1. 30.6 1.5 1381100200020 4509. 1. 16.6 0.8 1381100200021 3883. 2. 0.8 0.1 1381100200022 3855. 2. 1.0 0.1 1381100200023 3678. 1. 15.9 0.8 1381100200024 3532. 1. 9.9 0.5 1381100200025 2830. 2. 2.0 0.2 1381100200026 2521. 2. 6.1 0.3 1381100200027 1997. 2. 4.6 0.2 1381100200028 1989. 2. 1.5 0.3 1381100200029 1885. 1. 19.7 1.0 1381100200030 1857. 2. 0.8 0.2 1381100200031 1679. 2. 9.2 0.5 1381100200032 ENDDATA 25 0 1381100200033 ENDSUBENT 32 0 1381100299999 SUBENT 13811003 20010629 13361381100300001 BIB 2 2 1381100300002 REACTION (6-C-12(N,G)6-C-13,,SPC,,SPA) 1381100300003 SAMPLE Natural Graphite 1381100300004 ENDBIB 2 0 1381100300005 NOCOMMON 0 0 1381100300006 DATA 3 3 1381100300007 E DATA DATA-ERR 1381100300008 KEV PC/REAC PC/REAC 1381100300009 4945. 66. 3. 1381100300010 3684. 34. 2. 1381100300011 1262. 34. 2. 1381100300012 ENDDATA 5 0 1381100300013 ENDSUBENT 12 0 1381100399999 SUBENT 13811004 20010629 13361381100400001 BIB 2 3 1381100400002 REACTION (6-C-13(N,G)6-C-14,,SPC,,SPA) 1381100400003 SAMPLE Natural graphite (1.1% 13C) and 1-g sample of 13C that 1381100400004 is 94% isotopically pure. 1381100400005 ENDBIB 3 0 1381100400006 NOCOMMON 0 0 1381100400007 DATA 4 2 1381100400008 E E-ERR DATA DATA-ERR 1381100400009 KEV KEV PC/REAC PC/REAC 1381100400010 8174. 2. 87. 5. 1381100400011 6093. 2. 13. 1. 1381100400012 ENDDATA 4 0 1381100400013 ENDSUBENT 12 0 1381100499999 SUBENT 13811005 20010629 00001381100500001 BIB 2 2 1381100500002 REACTION (5-B-10(N,G)5-B-11,,SPC,,SPA) 1381100500003 SAMPLE Sample enriched of 10B (91.6%) 1381100500004 ENDBIB 2 0 1381100500005 NOCOMMON 0 0 1381100500006 DATA 4 8 1381100500007 E E-ERR DATA DATA-ERR 1381100500008 KEV KEV PC/REAC PC/REAC 1381100500009 11447. 2. 6. 1. 1381100500010 8916. 2. 15. 2. 1381100500011 7006. 2. 54. 3. 1381100500012 6739. 2. 19. 1. 1381100500013 4711. 2. 25. 1. 1381100500014 4444. 2. 65. 3. 1381100500015 2534. 2. 15. 2. 1381100500016 2295. 2. 10. 3. 1381100500017 ENDDATA 10 0 1381100500018 ENDSUBENT 17 0 1381100599999 SUBENT 13811006 20010629 00001381100600001 BIB 2 3 1381100600002 REACTION (3-LI-6(N,G)3-LI-7,,SPC,,SPA) 1381100600003 SAMPLE 99% isotopically pure samples of 6Li in the chemical 1381100600004 form Li(2)CO(3). 1381100600005 ENDBIB 3 0 1381100600006 NOCOMMON 0 0 1381100600007 DATA 4 2 1381100600008 E E-ERR DATA DATA-ERR 1381100600009 KEV KEV PC/REAC PC/REAC 1381100600010 7247. 2. 61. 3. 1381100600011 6769. 2. 39. 2. 1381100600012 ENDDATA 4 0 1381100600013 ENDSUBENT 12 0 1381100699999 ENDENTRY 6 0 1381199999999