ENTRY 12874 19850422 00001287400000001 SUBENT 12874001 19850422 00001287400100001 BIB 13 31 1287400100002 INSTITUTE (1USAORL) 1287400100003 REFERENCE (J,NSE,89,79,8501) 1287400100004 AUTHOR (R.L.MACKLIN) 1287400100005 TITLE NEUTRON CAPURE MEASUREMENTS ON FISSION-PRODUCT 107-PD. 1287400100006 FACILITY (LINAC) ORELA FACILITY AT ORNL. 1287400100007 INC-SOURCE (PHOTO)-WATER MODERATED 1287400100008 SAMPLE THE SAMPLE WAS PACKAGED IN A 0.1 MM THICK PLASTIC 1287400100009 ENVELOPE AND WAS 15.54+-0.05 PERCENT ISOTOPIC PURITY.1287400100010 NATURAL PALLADIUM SAMPLE WAS RUN INTERMIITTENTLY IN 1287400100011 THE LOWER ENERGY RANGE. 1287400100012 METHOD (TOF) TIME OF FLIGHT 40127 MM.PATH LENGTH. 1287400100013 THE TIME OF FLIGHT ENERGY SCALE WAS CALIBRATED 1287400100014 WITH ALUMINUM RESONANCES AT 5.903 AND 1094 KEV. 1287400100015 DETECTOR (SCIN) A PAIR OF NONHYDROGENOUS LIQUID SCINTILLATORS. 1287400100016 THE DETECTION EFFICIENCY WAS DETERMINED BY THE 1287400100017 SATURATED RESONANCE METHOD. 1287400100018 MONITOR LI-6 GLASS SCINTILLATOR WAS USED AS A NEUTRON FLUX 1287400100019 MONITOR. 1287400100020 CORRECTION THE DATA WERE CORRECTED FOR- 1287400100021 1. ELECTRONIC DEAD TIME. 1287400100022 2. MEASURED ENVIRONMENTAL BAKGROUND. 1287400100023 3. BEAM-DEPENDENT BACKGROUND. 1287400100024 4. GAMMA-RAY ENERGY LOSS IN THE SAMPLE. 1287400100025 A B-10 FILTER WAS USED TO ABSORB THE NEUTRONS FROM 1287400100026 EARLIER PULSES WHICH WOULD HAVE REACHED THE SAMPLE 1287400100027 AT THE SAME TIME AS THOSE BEING STUDIED. 1287400100028 STATUS DATA TAKEN FROM TABLES 2,3 AND 4 FROM THE PRE-PRINT 1287400100029 SUBMITTED TO NUC.SCI.ENG. 1287400100030 (APRVD) R.L.MACKLIN, 84/6/19. 1287400100031 HISTORY (840514C) 1287400100032 (850422A) REFERENCE UPDATE. 1287400100033 ENDBIB 31 0 1287400100034 NOCOMMON 0 0 1287400100035 ENDSUBENT 34 0 1287400199999 SUBENT 12874002 19841024 00001287400200001 BIB 5 23 1287400200002 REACTION 1(46-PD-107(N,0),,EN) 1287400200003 2(46-PD-107(N,G),,ARE) 1287400200004 3(46-PD-107(N,TOT),,WID) 1287400200005 ANALYSIS BREIT-WIGNER RESONANCE ANALYSIS WITH DOPPLER 1287400200006 BROADENING,SAMPLE THICKNESS AND EXPERIMENTAL 1287400200007 RESOLUTION WHICH WAS TAKEN TO BE A CONVOLUTION 1287400200008 OF GAUSSIAN AND EXPONENTIAL SHAPES. 1287400200009 COMPARISON WITH NATURAL PALLADIUM ENABLED THE 1287400200010 IDENTIFICATION OF PD-107 RESONANCES AS OPPOSED TO 1287400200011 PD-105. ANY PD-107 PEAKS UNDERLYING THE MOST 1287400200012 ABUNDANT EVEN ISOTOPE PD-106 PEAKS WERE NOT 1287400200013 IDENTIFIED. 1287400200014 ERR-ANALYS (ERR-T) THE AUTHOR QUOTES THE UNCERTAINTIES AS 1287400200015 STANDARD DEVIATIONS. 1287400200016 SYSTEMATIC UNCERTAINTIES ASSOCIATED WITH APPARATUS 1287400200017 AND ANALYSIS HAVE BEEN DESCRIBED EARLIER-SEE 1287400200018 NUCL.SCI.ENG.,84,98,1983. 1287400200019 ADD-RES THE 30 KEV MAXWELLIAN CAPTURE CROSS SECTION IS 1287400200020 CALCULATED TO BE 1.34+-0.06 BARNS. 1287400200021 THE DILUTE RESONANCE INTEGRAL=108.1+-4.3 BARNS 1287400200022 OF WHICH 100.3 BARNS IS CONTRIBUTED BY THE 1287400200023 133 RESONANCES KNOWN. 1287400200024 HISTORY (841024A) DATA HEADING CORRECTED. 1287400200025 ENDBIB 23 0 1287400200026 NOCOMMON 0 0 1287400200027 DATA 5 130 1287400200028 DATA 1DATA 2ERR-T 2DATA 3DATA-ERR 3 1287400200029 EV MILLI-EV MILLI-EV EV EV 1287400200030 27.98 0.327 0.009 1287400200031 41.31 5.6 0.1 1287400200032 44.43 15.5 0.1 1287400200033 58.90 4.29 0.02 1287400200034 73.37 0.54 0.01 1287400200035 84.13 6.5 0.1 1287400200036 88.43 11.0 0.1 1287400200037 100.47 1.73 0.02 1287400200038 114.79 8.11 0.05 1287400200039 132.0 1.79 0.02 1287400200040 140.3 10.7 0.1 1287400200041 152.2 18.9 0.1 1287400200042 172.5 27.3 0.1 1287400200043 173.9 3.16 0.04 1287400200044 181.5 15.7 0.1 1287400200045 196.1 2.37 0.03 1287400200046 211.2 0.99 0.02 1287400200047 223.0 5.19 0.05 1287400200048 226.5 19.9 0.1 1287400200049 232.3 7.8 0.1 1287400200050 266.9 3.65 0.06 1287400200051 271.6 3.41 0.06 1287400200052 291.7 15.8 0.1 1287400200053 294.7 20.0 0.1 1287400200054 300.7 6.7 0.1 1287400200055 314.4 8.6 0.1 1287400200056 325.1 19.7 0.1 1287400200057 344.0 8.6 0.2 1287400200058 356.7 18.3 0.3 1287400200059 368.7 25.8 0.2 1287400200060 375.7 7.7 0.1 1287400200061 380.3 8.4 0.1 1287400200062 434.7 8.1 0.1 1287400200063 472.0 21.0 0.1 1287400200064 479.1 2.8 0.1 1287400200065 488.6 13.0 0.1 1287400200066 507.1 20.5 0.2 1287400200067 518.4 50.6 0.3 1287400200068 520.6 33.0 0.2 1287400200069 538.0 14.6 0.1 1287400200070 558.4 27.7 0.1 1287400200071 569.2 25.1 0.3 1287400200072 586.5 16.0 0.2 1287400200073 627.2 30.2 0.1 1287400200074 633.3 19.7 0.3 1287400200075 653.7 35.1 0.2 1287400200076 665.0 35.6 0.4 1287400200077 679.3 35.1 0.2 1287400200078 701.7 27.6 0.3 1287400200079 719.7 38.5 0.4 1287400200080 802.4 27.4 0.3 1287400200081 813.0 9.3 0.3 1287400200082 851.1 5.9 0.1 1287400200083 878.2 53.0 0.3 1287400200084 883.7 2.8 0.1 1287400200085 910.6 17.1 0.2 1287400200086 917.9 9.4 0.2 1287400200087 1010.5 19.6 0.3 1287400200088 1021.1 38.3 0.5 1287400200089 1027.2 8.6 0.3 1287400200090 1079.3 8.5 0.6 1287400200091 1082.0 33.7 0.8 1287400200092 1117.5 14.2 0.4 1287400200093 1145.2 31.3 0.3 1287400200094 1206.5 26.4 0.4 1287400200095 1298.1 23.4 0.7 1287400200096 1322.5 11.3 0.3 1287400200097 1367.8 41.2 0.3 1287400200098 1407.3 20.4 0.5 1287400200099 1428.7 24.3 0.3 1287400200100 1464.2 10.6 1.5 1287400200101 1494.8 35.4 0.4 1287400200102 1502.0 31.3 0.4 1287400200103 1555.2 27.5 0.5 1287400200104 1596.0 42.1 0.8 1287400200105 1616.3 19.0 1.5 1287400200106 1701.0 26.4 0.7 1287400200107 1705.7 20.7 1.5 1287400200108 1718.0 12.4 1.6 1287400200109 1721.3 43.2 0.7 1287400200110 1742.2 10.7 1.6 1287400200111 1806.7 63.3 0.9 1287400200112 1809.4 32.7 0.8 1287400200113 1826.9 51.8 0.4 1287400200114 1853.3 39.6 0.8 1287400200115 1857.3 13.1 1.8 1287400200116 1863.1 12.3 1.2 1287400200117 1886.2 73.5 1.3 1287400200118 1896.8 63.5 0.8 1287400200119 1915.3 32.2 0.6 1287400200120 1921.4 21.8 1.4 1287400200121 2103.0 21.4 0.5 1287400200122 2223.9 14.1 0.6 1287400200123 2266.5 38.8 1.0 1287400200124 2272.0 43.7 0.6 1287400200125 2343.6 84.7 2.4 1287400200126 2412.9 32.5 3.9 1287400200127 2565.9 48.6 0.7 1287400200128 2694. 126.6 4.9 4.8 0.3 1287400200129 2737. 27.2 4.3 1287400200130 2743. 39.5 1.4 1287400200131 2768. 55.8 5.3 1287400200132 2787. 41.4 5.6 1.1 0.2 1287400200133 2836. 46.5 3.9 4.0 0.6 1287400200134 2879. 44.7 3.8 2.4 0.3 1287400200135 2888. 37.3 2.6 1287400200136 2902. 30.7 3.1 1.4 0.2 1287400200137 2961. 49.5 1.7 2.6 0.2 1287400200138 2993. 58.1 2.6 1287400200139 3040. 87.2 3.9 1287400200140 3082. 54.1 2.2 1287400200141 3117. 38.5 2.2 1287400200142 3141. 92.8 4.4 5.1 0.5 1287400200143 3161. 46.5 5.1 5.5 1.0 1287400200144 3181. 30.1 3.4 1287400200145 3268. 14.7 2.0 1287400200146 3276. 47.5 2.2 1287400200147 3293. 34.0 3.7 1287400200148 3303. 10.0 3.8 1287400200149 3322. 133.9 10.8 5.5 0.7 1287400200150 3330. 27.2 4.7 1287400200151 3342. 10.6 1.8 1287400200152 3355. 117.7 5.5 5.1 0.4 1287400200153 3399. 59.7 3.9 1287400200154 3430. 48.4 3.9 1287400200155 3443. 86.9 4.0 3.1 0.2 1287400200156 3454. 28.1 3.6 1287400200157 3466. 99.6 13.3 8.3 1.4 1287400200158 3499. 9.8 2.6 1287400200159 3510. 121.5 4.2 3.3 0.2 1287400200160 ENDDATA 132 0 1287400200161 ENDSUBENT 160 0 1287400299999 SUBENT 12874003 19840514 00001287400300001 BIB 3 21 1287400300002 REACTION (46-PD-107(N,G)46-PD-108,,SIG,,AV) 1287400300003 ANALYSIS THE AVERAGE PD-107 CAPTURE CROSS SECTIONS WERE DERIVED 1287400300004 FROM THE FISSION PRODUCT SAMPLE DATA BY SUBTRACTING 1287400300005 THE 104,105,106,108,110PD CAPTURE YIELDS WITH THE 1287400300006 HELP OF THE LINEAR UNSCRAMBLING MATRIX OBTAINED BY 1287400300007 THE AUTHOR PREVIOUSLY-SEE NUC.SCI.ENG.,71,182,1979. 1287400300008 ABOVE 2600 EV THE ENRICHED STABLE ISOTOPE CAPTURE 1287400300009 DATA(NUCL.SCI.ENG.,86,362,1984) WERE LINEARLY 1287400300010 COMBINED WITH THE FISSION PRODUCT DATA TO GIVE THE 1287400300011 NET CAPTURE YIELD DUE TO PD-107 ALONE. 1287400300012 ERR-ANALYS (ERR-S) STATISTICAL UNCERTAINTIES. 1287400300013 (ERR-1) SYSTEMATIC UNCERTAINTY DUE TO SAMPLE RELATED 1287400300014 CORRECTIONS ARE- 1287400300015 1. NON-LINEAR NEUTRON ABSORPTION,SCATTERING. 1287400300016 2. 2.4 PERCENT DUE TO NORMALIZATION. 1287400300017 3. 2.4 PERCENT DUE TO SUBTRACTION OF RUNS 1287400300018 MADE WITH DIFFFERENT SAMPLES AND THE 1287400300019 FLUX SHAPE UNCERTAINTIES. 1287400300020 THE UNCERTAINTIES ARE GIVEN AT THE 68 PERCENT 1287400300021 PROBABILITY LEVEL OR ONE STANDARD DEVIATION OF A 1287400300022 GAUSSIAN DISTRIBUTION. 1287400300023 ENDBIB 21 0 1287400300024 NOCOMMON 0 0 1287400300025 DATA 5 17 1287400300026 EN-MIN EN-MAX DATA ERR-S ERR-1 1287400300027 KEV KEV MB MB MB 1287400300028 3. 4. 3067. 40. 137. 1287400300029 4. 6. 2740. 36. 105. 1287400300030 6. 8. 2481. 34. 83. 1287400300031 8. 10. 2317. 32. 68. 1287400300032 10. 15. 1968. 28. 54. 1287400300033 15. 20. 1826. 26. 46. 1287400300034 20. 30. 1531. 22. 36. 1287400300035 30. 40. 1273. 18. 28. 1287400300036 40. 60. 1082. 16. 22. 1287400300037 60. 80. 918. 14. 18. 1287400300038 80. 100. 798. 12. 16. 1287400300039 100. 150. 639. 10. 14. 1287400300040 150. 200. 532. 9. 11. 1287400300041 200. 300. 460. 8. 7. 1287400300042 300. 400. 298. 6. 4. 1287400300043 400. 500. 155. 6. 1. 1287400300044 500. 600. 114. 6. 0. 1287400300045 ENDDATA 19 0 1287400300046 ENDSUBENT 45 0 1287400399999 SUBENT 12874004 19860114 00001287400400001 BIB 4 6 1287400400002 REACTION 1(46-PD-106(N,0),,EN) 1287400400003 2(46-PD-106(N,G),,WID) 1287400400004 3(46-PD-106(N,EL),,WID,,G) 1287400400005 ANALYSIS BREIT-WIGNER ANALYSIS ON NATURAL PD SAMPLE. 1287400400006 ERR-ANALYS (ERR-T) STANDARD DEVIATION 1287400400007 HISTORY (860114A) DATA HEADING CORRECTED. 1287400400008 ENDBIB 6 0 1287400400009 NOCOMMON 0 0 1287400400010 DATA 5 1 1287400400011 DATA 1DATA 2ERR-T 2DATA 3ERR-T 3 1287400400012 EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 1287400400013 282.1 85.0 0.6 519. 4. 1287400400014 ENDDATA 3 0 1287400400015 ENDSUBENT 14 0 1287400499999 ENDENTRY 4 0 1287499999999