SUBENT 12915001 19860107 00001291500100001
BIB 14 58 1291500100002
INSTITUTE (1USAORL) 1291500100003
REFERENCE (J,ASP,115,71,85) 1291500100004
AUTHOR (R.L.MACKLIN) 1291500100005
TITLE NEUTRON CAPTURE MEASUREMENTS ON RADIOACTIVE 42-ZR-93. 1291500100006
FACILITY (LINAC) ORELA LINEAR ACCELERATOR. 1291500100007
INC-SOURCE (EVAP) UNCERTAINTY OF THE NEUTRON ENERGY SCALE=1/1300.1291500100008
SAMPLE FISSION PRODUCT ZR-93- 1.5*10**6 YEAR 1291500100009
6.595 G OF POWDER PRESSED INTO A 25.4-MM-DIAMETER BY1291500100010
3.5-MM-THICK DISC. 1291500100011
SAMPLE IMPURITIES- 1291500100012
NUCLEUS WEIGHT PERCENT 1291500100013
ZR-90 1.5 1291500100014
ZR-91 19.0 1291500100015
ZR-92 20.0 1291500100016
ZR-93 20.0 1291500100017
ZR-94 20.0 1291500100018
ZR-96 19.0 1291500100019
HF 0.2 1291500100020
MO 1.0 1291500100021
NB - 1291500100022
FE 0.3 1291500100023
CR 0.07 1291500100024
SI 5.0 1291500100025
AL 1.0 1291500100026
HIGH BACKGROUND COUNTING(5300C/S) FROM SAMPLE 1291500100027
IMPURITIES. 1291500100028
METHOD (TOF) TIME-OF-FLIGHT ENERGY SCALE CALIBRATED WITH 1291500100029
ALUMINUM RESONANCES AT 5.903 AND 1094 KEV. 1291500100030
DETECTOR (SCIN) NONHYDROGENOUS LIQUID SCINTILLATOR 1291500100031
EFFICIENCY DETERMINED BY THE SATURATED 1291500100032
RESONANCE METHOD RELATIVE TO A THIN LI-6 GLASS 1291500100033
SCINTILLATOR AS A NEUTRON FLUX MONITOR. 1291500100034
MONITOR LI-6 GLASS SCINTILLATOR 1291500100035
CORRECTION DATA WERE CORRECTED FOR- 1291500100036
. ELECTRONIC DEAD TIME 1291500100037
. MEASURED ENVIRONMENTAL AND SAMPLE RADIOACTIVITY. 1291500100038
. BEAM-DEPENDENT BACKGROUNDS 1291500100039
. GAMMA-RAY ENERGY LOSS IN THE SAMPLE MATERIAL 1291500100040
ERR-ANALYS (DATA-ERR) STANADRD DEVIATIONS. 1291500100041
SOURCES OF ERROR- 1291500100042
. CALIBRATION UNCERTAINTIES = 3.1 PERCENT 1291500100043
1. 1 PERCENT DUE TO CROSS CALIBRATION TO ZR-911291500100044
AT 292 EV ENERGY IN THE METAL SAMPLE 1291500100045
SAMPLE DATA. 1291500100046
2. 1.4 PERCENT IN THE FISSION-PRODUCT 1291500100047
SAMPLE DATA. 1291500100048
3. 0.6 PERCENT DUE TO SCATTERED NEUTRON 1291500100049
SENSITIVITY CORRECTION. 1291500100050
4. 0.7 PERCENT UNCERTAINTY DUE TO ABUNDANCE 1291500100051
RATIO. 1291500100052
. ABOVE 21.5 KEV THE RESIDUAL BACKGROUND UNCERTAINTY 1291500100053
= 8 PERCENT 1291500100054
. ABOVE 95 KEV THE AVERAGE ZR-96 CAPTURE SUBTRACTION 1291500100055
UNCERTAINTY IS ASSUMED = 0.7 PERCENT OF THE 1291500100056
ZR-93 NET CROSS SECTION. 1291500100057
STATUS (APRVD) R.L.MACKLIN, 85/3/27. 1291500100058
HISTORY (850227C) 1291500100059
(860107U) REFERENCE UPDATED 1291500100060
ENDBIB 58 0 1291500100061
NOCOMMON 0 0 1291500100062
ENDSUBENT 61 0 1291500199999
SUBENT 12915003 19860107 00001291500300001
BIB 3 3 1291500300002
REACTION (40-ZR-93(N,G)40-ZR-94,,SIG,,AV) 1291500300003
STATUS POINTWISE DATA NOT AVAILABLE. 1291500300004
HISTORY (860107U) REACTION PRODUCT ADDED 1291500300005
ENDBIB 3 0 1291500300006
NOCOMMON 0 0 1291500300007
DATA 4 14 1291500300008
EN-MIN EN-MAX DATA DATA-ERR 1291500300009
KEV KEV MB MB 1291500300010
3. 4. 507. 8. 1291500300011
4. 6. 468. 5. 1291500300012
6. 8. 298. 4. 1291500300013
8. 10. 171. 3. 1291500300014
10. 15. 196. 3. 1291500300015
15. 20. 116. 3. 1291500300016
20. 30. 115. 16. 1291500300017
30. 40. 115. 13. 1291500300018
40. 60. 64. 11. 1291500300019
60. 80. 39. 9. 1291500300020
80. 100. 32. 8. 1291500300021
100. 150. 19. 7. 1291500300022
150. 200. 27. 6. 1291500300023
200. 300. 27. 5. 1291500300024
ENDDATA 16 0 1291500300025
ENDSUBENT 24 0 1291500399999