ENTRY 20864 20200925 22912086400000001 SUBENT 20864001 20200925 22912086400100001 BIB 14 89 2086400100002 TITLE Cross section measurements for the reaction 2086400100003 Rh-103(n,n')Rh-103m 2086400100004 AUTHOR (A.Paulsen,R.Widera,R.Vaninbroukx,H.Liskien) 2086400100005 REFERENCE (J,NSE,76,331,1980) 2086400100006 (W,PAULSEN,19781025) 2086400100007 ((P,INDC(EUR)-10,3,1976)=(P,NEANDC(E)-182,(3),3,1977))-2086400100008 prelim. data at En=1.80MeV 2086400100009 INSTITUTE (2ZZZGEL) 2086400100010 FACILITY (VDG,2ZZZGEL) 7 MV Van der Graaff of the CBNM. 2086400100011 INC-SOURCE (P-LI7) Neutron energies 0.2 MeV to 0.4 MeV 2086400100012 (D-T) neutron energies 0.3 MeV to 2.9 MeV 2086400100013 (D-D) neutron energies 1.9 MeV to 4.1 MeV 2086400100014 (P-T) neutron energies 3.6 MeV to 6.1 MeV 2086400100015 (D-T) neutron energies 13.0 MeV to 16.7 MeV 2086400100016 solid targets of lithium fluoride, deuterium, or 2086400100017 tritium occluded in titanium or yttrium layers, 2086400100018 on a 0.3 mm thick silver or molybdenum backing. 2086400100019 SAMPLE Metallic rhodium-103, 99.9% pure, 20 mm diam., 2086400100020 5 mm thick used for relative activity 2086400100021 measurements. 0.1 mm thick samples used for 2086400100022 absolute cross section measurement. 2086400100023 METHOD (ACTIV) A pair of samples at each neutron emission 2086400100024 angle ( corresponding to nominal neutron energies 2086400100025 in 100 keV steps ) was irradiated for about 1 hour. 2086400100026 1000 sec delay after irradiation allowed for decay 2086400100027 of any Rh-104 present. X-rays then counted for 2086400100028 about 30 periods of 5 minutes. This allowed the 2086400100029 half-life to be checked against the standard used. 2086400100030 Relative cross sections calculated from relative 2086400100031 activities. 2086400100032 For absolute cross section measurement three pairs 2086400100033 of rhodium samples irradiated with 1.80 MeV neutrons 2086400100034 from p-t source. Activation of samples measured with 2086400100035 Si-Li counters for at least 5 periods of 1000 to 2086400100036 2000 sec during a period 0.2 to 2 hours after 2086400100037 irradiation. Activities checked after 20 hours to 2086400100038 confirm the absence of long term activity. 2086400100039 Si-Li detectors calibrated against thin 99.9% 2086400100040 pure Rh-103m sources whose activities had been 2086400100041 determined by liquid scintillation counting. 2086400100042 Neutron flux from source measured by a recoil proton 2086400100043 telescope counter 25 m away. Time dependence of 2086400100044 neutron flux during sample irradiation was monitored 2086400100045 with a directional long counter. 2086400100046 DETECTOR (SCIN ) Na-I(Tl) scintillation crystals used to 2086400100047 measure relative activities of samples 2086400100048 irradiated by neutrons of different energy. 2086400100049 (SILI) Si-Li detectors with full-width-half-maximum 2086400100050 resolution of 600 eV at 20 keV used to measure 2086400100051 activity of samples for absolute cross 2086400100052 section measurement. 2086400100053 (TELES,SOLST,SOLST) Recoil proton telescope counter and2086400100054 (LONGC) long counter used to measure neutron flux 2086400100055 for absolute cross section measurement 2086400100056 DECAY-DATA (45-RH-103-M,56.116MIN,XR) Hl from Appl.Rad.Isot.,24,872086400100057 E.Gunther+, and confirmed during the measurements. 2086400100058 MONITOR (45-RH-103(N,INL)45-RH-103-M,,SIG) Three irradiations 2086400100059 at 1.80-MeV neutron energy and successive activity 2086400100060 determinations of a sample pair yielded, as an average,2086400100061 817 mb with a standard error of the mean of 1.4%. 2086400100062 CORRECTION Background neutrons produced by target. 2086400100063 Neutron scatter from target backing. (> 2% for 2086400100064 several cases in the range 0.3 to 0.2 MeV ) 2086400100065 Multiple scatter in sample. 2086400100066 Difference between X-ray detection efficiencies 2086400100067 for samples used in relative and absolute 2086400100068 measurements. 2086400100069 Self-absorption of X-rays within the active 2086400100070 sample in the absolute cross section measurement. 2086400100071 Correction determined by measuring x-rays from 2086400100072 Pd-103 foils stacked together, and comparing with 2086400100073 simple theory. This is the most important correction. 2086400100074 ERR-ANALYS (ERR-T) Total error includes: 2086400100075 (ERR-1) Error in radiation geometry. 2086400100076 (ERR-2) Error in angular distribution. 2086400100077 (ERR-3) Error in neutron flux determination. 2086400100078 (ERR-4) Error in sample purity. 2086400100079 (ERR-5) Error in detector efficiency. 2086400100080 (MONIT-ERR) Total error in the monitor value, computed 2086400100081 by quadratically summing the above + stat. error (1.4%)2086400100082 HISTORY (19790319C) WWO. 2086400100083 (19820118A) A.P.T. BIB section rewritten after full 2086400100084 paper published. Data, which was arbitrarily normalised2086400100085 replaced by data normalized to a measured value. 2086400100086 (19860227U)N.Ch 2086400100087 (20200925A) SD:Updated to new date formats, lower case.2086400100088 Corrections in all Subents. BIB updated. The accuracy 2086400100089 of data presentation has been revised. Three refs on 2086400100090 progress reports deleted (no data). EN-NRM added. 2086400100091 ENDBIB 89 0 2086400100092 COMMON 8 6 2086400100093 EN-NRM MONIT MONIT-ERR ERR-1 ERR-2 ERR-3 2086400100094 ERR-4 ERR-5 2086400100095 MEV MB PER-CENT PER-CENT PER-CENT PER-CENT 2086400100096 PER-CENT PER-CENT 2086400100097 1.80 817. 3.6 1.5 1.0 2.5 2086400100098 0.1 1.2 2086400100099 ENDCOMMON 6 0 2086400100100 ENDSUBENT 99 0 2086400199999 SUBENT 20864002 20200925 22912086400200001 BIB 4 5 2086400200002 REACTION (45-RH-103(N,INL)45-RH-103-M,,SIG) 2086400200003 INC-SPECT +-EN-RSL - The total width given, covers the full 2086400200004 range of the neutron energy spectrum seen by the sample2086400200005 STATUS (TABLE) Tbl.III from Nucl.Sci.Eng.,76(1980)331 2086400200006 HISTORY (20200925U) SD: STATUS updated. DATA-ERR -> ERR-T. 2086400200007 ENDBIB 5 0 2086400200008 NOCOMMON 0 0 2086400200009 DATA 6 67 2086400200010 EN EN-ERR +EN-RSL -EN-RSL DATA ERR-T 2086400200011 MEV MEV MEV MEV MB PER-CENT 2086400200012 0.199 0.003 0.023 0.024 74. 8.02086400200013 0.250 0.003 0.024 0.028 103. 7.22086400200014 0.300 0.004 0.025 0.024 119. 7.02086400200015 0.350 0.003 0.021 0.020 124. 7.52086400200016 0.399 0.004 0.029 0.025 129. 7.12086400200017 0.500 0.005 0.063 0.053 151. 6.02086400200018 0.601 0.005 0.042 0.037 238. 5.12086400200019 0.703 0.005 0.070 0.067 368. 4.62086400200020 0.802 0.007 0.058 0.049 525. 4.62086400200021 0.903 0.008 0.095 0.100 593. 4.62086400200022 1.006 0.008 0.114 0.097 613. 4.62086400200023 1.10 0.01 0.11 0.11 576. 4.92086400200024 1.20 0.01 0.11 0.11 631. 4.92086400200025 1.30 0.01 0.11 0.11 619. 4.72086400200026 1.40 0.01 0.14 0.14 726. 4.62086400200027 1.50 0.01 0.09 0.09 729. 4.72086400200028 1.60 0.01 0.08 0.08 718. 4.62086400200029 1.70 0.01 0.17 0.17 805. 4.62086400200030 1.80 0.01 0.18 0.18 817. 3.62086400200031 1.90 0.01 0.12 0.12 800. 4.72086400200032 2.00 0.01 0.10 0.10 844. 4.72086400200033 2.10 0.01 0.18 0.18 867. 4.62086400200034 2.20 0.01 0.10 0.10 885. 4.62086400200035 2.30 0.01 0.14 0.14 916. 4.82086400200036 2.40 0.01 0.17 0.17 927. 4.62086400200037 2.50 0.01 0.16 0.16 898. 4.62086400200038 2.60 0.01 0.15 0.15 994. 4.62086400200039 2.70 0.01 0.13 0.13 974. 4.62086400200040 2.80 0.01 0.17 0.17 950. 4.62086400200041 2.90 0.01 0.18 0.18 1059. 4.52086400200042 3.00 0.02 0.19 0.19 1034. 5.12086400200043 3.10 0.02 0.20 0.20 1039. 4.92086400200044 3.20 0.02 0.21 0.21 1052. 4.82086400200045 3.30 0.02 0.21 0.21 1000. 5.12086400200046 3.40 0.02 0.22 0.22 1038. 4.92086400200047 3.50 0.02 0.23 0.23 1049. 4.92086400200048 3.60 0.02 0.24 0.24 1022. 4.82086400200049 3.70 0.03 0.25 0.25 1031. 4.92086400200050 3.80 0.03 0.26 0.26 1075. 4.82086400200051 3.90 0.03 0.27 0.27 1045. 4.82086400200052 4.00 0.03 0.28 0.28 1077. 4.72086400200053 4.10 0.03 0.29 0.29 1094. 4.72086400200054 4.20 0.03 0.34 0.34 1140. 6.12086400200055 4.30 0.03 0.34 0.34 1250. 5.92086400200056 4.40 0.03 0.34 0.34 1122. 6.32086400200057 4.50 0.03 0.34 0.34 1066. 5.92086400200058 4.60 0.03 0.34 0.34 1064. 5.82086400200059 4.70 0.03 0.33 0.33 1139. 5.82086400200060 4.80 0.03 0.33 0.33 1080. 5.92086400200061 4.90 0.03 0.33 0.33 1194. 5.72086400200062 5.00 0.03 0.32 0.32 1163. 5.82086400200063 5.10 0.03 0.31 0.31 1164. 6.22086400200064 5.20 0.03 0.30 0.30 1017. 5.82086400200065 5.30 0.03 0.29 0.29 1003. 5.72086400200066 5.40 0.03 0.28 0.28 1136. 5.52086400200067 5.50 0.03 0.27 0.27 1117. 5.52086400200068 5.60 0.03 0.25 0.25 1259. 5.72086400200069 5.70 0.02 0.23 0.23 1150. 5.42086400200070 5.80 0.02 0.21 0.21 1077. 5.62086400200071 5.90 0.02 0.19 0.19 1111. 5.42086400200072 6.00 0.01 0.15 0.15 1239. 5.42086400200073 6.10 0.01 0.11 0.11 1207. 5.42086400200074 13.00 0.01 0.18 0.18 398. 9.42086400200075 14.00 0.00 0.25 0.25 286. 9.52086400200076 15.00 0.01 0.29 0.29 244. 9.52086400200077 16.00 0.03 0.31 0.31 222. 9.52086400200078 16.70 0.03 0.30 0.30 226. 9.52086400200079 ENDDATA 69 0 2086400200080 ENDSUBENT 79 0 2086400299999 ENDENTRY 2 0 2086499999999