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 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