ENTRY 13831 20020501 00001383100000001 SUBENT 13831001 20020501 00001383100100001 BIB 17 38 1383100100002 INSTITUTE (1USAANL) 1383100100003 REFERENCE (J,PR,146,844,196606) 1383100100004 AUTHOR (A.Namenson,H.E.Jackson,R.K.Smither) 1383100100005 TITLE High-Energy Gamma Spectra Resulting from Neutron 1383100100006 Capture in Hafnium Isotopes. 1383100100007 FACILITY (REAC) In-pile facility at the Argonne CP-5 research 1383100100008 reactor. 1383100100009 INC-SOURCE (REAC) Core of CP-5 research reactor with a thermal 1383100100010 neutron flux ~3E+13 n/(cm2.s) at the sample position. 1383100100011 INC-SPECT Reactor spectrum. 1383100100012 METHOD Data collected as a series of runs of relatively short 1383100100013 duration (~3h) to avoid drifts. Collimators reduced 1383100100014 ratio of the 'aluminum' background to hafnium capture 1383100100015 lines to 10-20%. 1383100100016 Isotopic identification of gamma lines based on the 1383100100017 variation in their intensities from sample to sample. 1383100100018 DETECTOR (GELI) Lithium-drifted germanium detector with a volume1383100100019 of 1.0 cc, installed in a vacuum chamber and cooled to1383100100020 liquid nitrogen temperature; resolution width of 1383100100021 system ~6 keV at 7.7 MeV and ~3 keV at 1 MeV. 1383100100022 MONITOR (72-HF-178(N,G)72-HF-179,,SPC) Absolute intensity. 1383100100023 Pulser calibrated against the 7722-keV double-escape 1383100100024 peak of aluminum, which was determined from the 1383100100025 accurately measured value of the 10834.2-keV line in 1383100100026 nitrogen using BeN(3) sample (F.Everling+,1960). 1383100100027 Relative efficiency for detecting gamma rays as a 1383100100028 function of energy measured by studying capture 1383100100029 spectrum from BeN(3) and comparing it with that 1383100100030 reported in (Bartholomew+,1957). 1383100100031 MONIT-REF (,L.V.Groshev+,J,IZV,28,1244,1964) 1383100100032 CORRECTION Corrected for background, and for energy-dependent 1383100100033 effects due to detector efficiency. 1383100100034 ERR-ANALYS (E-ERR) Statistical uncertainties in gamma-ray energies1383100100035 REL-REF (R,,F.Everling+,J,NP,18,529,1960) 1383100100036 (R,,G.A.Bartholomew+,J,CJP,35,1347,1957) 1383100100037 ADD-RES Neutron separation energies determined. 1383100100038 STATUS Data taken from Table I, II, III, and V of reference. 1383100100039 HISTORY (20020405C) IS 1383100100040 ENDBIB 38 0 1383100100041 COMMON 2 3 1383100100042 EN-DUMMY E-ERR 1383100100043 EV KEV 1383100100044 0.0253 3. 1383100100045 ENDCOMMON 3 0 1383100100046 ENDSUBENT 45 0 1383100199999 SUBENT 13831002 20020501 00001383100200001 BIB 3 13 1383100200002 REACTION (72-HF-177(N,G)72-HF-178,,SPC,,SPA) 1383100200003 SAMPLE 300 mg powder of HfO sample enriched to 80% in Hf177, 1383100200004 contained into a sample holder made of an alloy of 1383100200005 ~85% Mg, 15% Al, which was fastened to a small 1383100200006 aluminum tube 1383100200007 ERR-ANALYS (DATA-ERR) Statistical uncertainties given. 1383100200008 In addition, the there are systematic uncertainties in 1383100200009 determining intensities due to errors in: 1383100200010 . intensity of the 5720-keV line in natural hafnium 1383100200011 as measured by Groshev+ 1383100200012 . efficiency curve, 1383100200013 . measured composition of targets, 1383100200014 . cross sections of the isotopes. 1383100200015 ENDBIB 13 0 1383100200016 COMMON 1 3 1383100200017 DATA-ERR 1383100200018 PER-CENT 1383100200019 20. 1383100200020 ENDCOMMON 3 0 1383100200021 DATA 2 25 1383100200022 E DATA 1383100200023 KEV PC/REAC 1383100200024 7530. 0.065 1383100200025 7317. 0.047 1383100200026 6445. 0.096 1383100200027 6354. 0.454 1383100200028 6301. 0.096 1383100200029 6239. 0.100 1383100200030 6214. 0.064 1383100200031 6191. 0.036 1383100200032 6172. 0.051 1383100200033 6110. 0.820 1383100200034 6091. 0.109 1383100200035 6063. 0.121 1383100200036 5985. 0.141 1383100200037 5863. 0.052 1383100200038 5802. 0.390 1383100200039 5759. 0.195 1383100200040 5751. 0.096 1383100200041 5707. 0.154 1383100200042 5679. 0.046 1383100200043 5666. 0.166 1383100200044 5635. 0.122 1383100200045 5623. 0.101 1383100200046 5610. 0.153 1383100200047 5602. 0.076 1383100200048 5574. 0.275 1383100200049 ENDDATA 27 0 1383100200050 ENDSUBENT 49 0 1383100299999 SUBENT 13831003 20020501 00001383100300001 BIB 3 13 1383100300002 REACTION (72-HF-179(N,G)72-HF-180,,SPC,,SPA) 1383100300003 SAMPLE 300 mg powder of HfO sample enriched to 83.6% in Hf179,1383100300004 contained into a sample holder made of an alloy of 1383100300005 ~85% Mg, 15% Al, which was fastened to a small 1383100300006 aluminum tube 1383100300007 ERR-ANALYS (DATA-ERR) Statistical uncertainties given. 1383100300008 In addition, the there are systematic uncertainties in 1383100300009 determining intensities due to errors in: 1383100300010 . intensity of the 5720-keV line in natural hafnium 1383100300011 as measured by Groshev+ 1383100300012 . efficiency curve, 1383100300013 . measured composition of targets, 1383100300014 . cross sections of the isotopes. 1383100300015 ENDBIB 13 0 1383100300016 COMMON 1 3 1383100300017 DATA-ERR 1383100300018 PER-CENT 1383100300019 20. 1383100300020 ENDCOMMON 3 0 1383100300021 DATA 2 13 1383100300022 E DATA 1383100300023 KEV PC/REAC 1383100300024 7074. 0.046 1383100300025 6742. 0.055 1383100300026 6231. 0.020 1383100300027 6203. 0.033 1383100300028 6196. 0.016 1383100300029 6190. 0.036 1383100300030 6123. 0.036 1383100300031 6095. 0.084 1383100300032 6012. 0.124 1383100300033 5953. 0.056 1383100300034 5915. 0.026 1383100300035 5842. 0.186 1383100300036 5773. 0.298 1383100300037 ENDDATA 15 0 1383100300038 ENDSUBENT 37 0 1383100399999 SUBENT 13831004 20020501 00001383100400001 BIB 3 16 1383100400002 REACTION (72-HF-178(N,G)72-HF-179,,SPC,,SPA) 1383100400003 SAMPLE Three samples used: 1383100400004 1) Natural hafnium metal foil target weighing ~800 mg 1383100400005 (27.08% 178Hf), 1383100400006 2) 300 mg HfO powder enriched to 80% in Hf177, (17.2% 1383100400007 178Hf) 1383100400008 3) 300 mg HfO powder enriched to 83.6% in Hf179 (4.6% 1383100400009 178Hf) 1383100400010 ERR-ANALYS (DATA-ERR) Statistical uncertainties given. 1383100400011 In addition, the there are systematic uncertainties in 1383100400012 determining intensities due to errors in: 1383100400013 . intensity of the 5720-keV line in natural hafnium 1383100400014 as measured by Groshev+ 1383100400015 . efficiency curve, 1383100400016 . measured composition of targets, 1383100400017 . cross sections of the isotopes. 1383100400018 ENDBIB 16 0 1383100400019 COMMON 1 3 1383100400020 DATA-ERR 1383100400021 PER-CENT 1383100400022 20. 1383100400023 ENDCOMMON 3 0 1383100400024 DATA 2 2 1383100400025 E DATA 1383100400026 KEV PC/REAC 1383100400027 5720. 8.75 1383100400028 5676. 1.49 1383100400029 ENDDATA 4 0 1383100400030 ENDSUBENT 29 0 1383100499999 SUBENT 13831005 20020501 00001383100500001 BIB 4 6 1383100500002 REACTION (72-HF-0(N,G),,SPC,,SPA) 1383100500003 SAMPLE Natural hafnium metal foil target weighing ~800 mg. 1383100500004 ERR-ANALYS Uncertainties of the line intensities not given. 1383100500005 FLAG (7.) Capture in 177Hf 1383100500006 (8.) Capture in 178Hf 1383100500007 (0.) Capture in 180Hf 1383100500008 ENDBIB 6 0 1383100500009 NOCOMMON 0 0 1383100500010 DATA 3 29 1383100500011 E DATA FLAG 1383100500012 KEV PC/REAC NO-DIM 1383100500013 7530. 0.045 7. 1383100500014 7317. 0.025 7. 1383100500015 6445. 0.058 7. 1383100500016 6354. 0.304 7. 1383100500017 6301. 0.070 7. 1383100500018 6239. 0.079 7. 1383100500019 6214. 0.048 7. 1383100500020 6191. 0.039 7. 1383100500021 6172. 0.044 7. 1383100500022 6110. 0.655 7. 1383100500023 6091. 0.130 7. 1383100500024 6063. 0.113 7. 1383100500025 5987. 0.128 7. 1383100500026 5863. 0.042 7. 1383100500027 5802. 0.249 7. 1383100500028 5759. 0.161 7. 1383100500029 5751. 0.072 7. 1383100500030 5720. 1.65 8. 1383100500031 5707. 0.181 7. 1383100500032 5693. 0.770 0. 1383100500033 5679. 0.031 7. 1383100500034 5676. 0.301 8. 1383100500035 5666. 0.108 7. 1383100500036 5647. 0.187 0. 1383100500037 5635. 0.109 7. 1383100500038 5623. 0.093 7. 1383100500039 5610. 0.132 7. 1383100500040 5602. 0.071 7. 1383100500041 5574. 0.306 7. 1383100500042 ENDDATA 31 0 1383100500043 ENDSUBENT 42 0 1383100599999 ENDENTRY 5 0 1383199999999