ENTRY 23570 20200415 22872357000000001 SUBENT 23570001 20200415 22872357000100001 BIB 12 26 2357000100002 TITLE Study on the reactor Neutron-induced fission of 231Pa 2357000100003 AUTHOR (J.Kemmer,J.I.Kim,H.-J.Born) 2357000100004 REFERENCE (J,RCA,13,181,1970) 2357000100005 INSTITUTE (2GERMUN) 2357000100006 FACILITY (REAC,2GERMUN) Munich research reactor 2357000100007 INC-SOURCE (REAC) 2357000100008 INC-SPECT Reactor neutrons. 2357000100009 Fast neutron flux 6.5E+12 n/(cm2*sec). 2357000100010 Thermal neutron flux 1.5E+13 n/(cm2*sec). 2357000100011 SAMPLE . Thin Pa layer 0.4 - 1.0 mg/cm2, total amount 1 mg. 2357000100012 Al foil as catcher of FF. 2357000100013 .Standard - 0.4 microg U-235 on Al foil, in quartz 2357000100014 ampoules of 1.3 mm2 x 20 mm. 2357000100015 . One thinner Pa sample in Cd box (int. 10x30x2 mm), 2357000100016 catcher on upper surface. To determine self-absorption.2357000100017 METHOD (GSPEC) Irradiation time 2 - 65 hr. 2357000100018 DETECTOR (GELI) 15 cm3 volume, energy resolution 3.5 keV at 2357000100019 662 keV. ORTEC118AFET preamplifier, ORTEC435A active 2357000100020 filter amplifier,Scipp 4096 pulse height analyzer of 2357000100021 Victoreen Co. 2357000100022 2048 channels for Pa-231, 2048 channels for U-235. 2357000100023 Used to measure gamma spectra of the fission products. 2357000100024 ADD-RES In test of catcher method the ratio of activities 2357000100025 catcher-foil/standard was measured and given in Table 12357000100026 for set of 16 nuclides. 2357000100027 HISTORY (20200415C) M.M. 2357000100028 ENDBIB 26 0 2357000100029 NOCOMMON 0 0 2357000100030 ENDSUBENT 29 0 2357000199999 SUBENT 23570002 20200415 22872357000200001 BIB 8 35 2357000200002 REACTION (91-PA-231(N,F)MASS,CHN,FY,,FST) 2357000200003 DECAY-DATA ((1.)36-KR-85-M,,DG,151.1) 2357000200004 ((2.)39-Y-91-M,,DG,555.7) 2357000200005 ((3.)40-ZR-95,,DG,724.5,,DG,756.6) 2357000200006 ((3.)41-NB-95,,DG,765.8) 2357000200007 ((4.)41-NB-97,,DG,743.3,,DG,658.1) 2357000200008 ((5.)42-MO-99,,DG,181.1) 2357000200009 ((5.)43-TC-99-M,,DG,140.5) 2357000200010 ((6.)44-RU-103,,DG,497.4) 2357000200011 ((7.)53-I-131,,DG,364.5) 2357000200012 ((8.)52-TE-132,,DG,228.2) 2357000200013 ((9.)53-I-133,,DG,529.9) 2357000200014 ((9.)54-XE-133,,DG,80.9) 2357000200015 ((10.)54-XE-135,,DG,249.7) 2357000200016 ((11.)55-CS-137,,DG,661.6) 2357000200017 ((12.)56-BA-140,,DG,162.8,,DG,537.0) 2357000200018 ((12.)57-LA-140,,DG,328.6) 2357000200019 ((13.)58-CE-141,,DG,145.6) 2357000200020 ((14.)58-CE-143,,DG,293.1) 2357000200021 ((15.)58-CE-144,,DG,133.4) 2357000200022 ((16.)60-ND-147,,DG,91.0) 2357000200023 ((17.)61-PM-149,,DG,286.0) 2357000200024 Uncertainty +-0.5 keV for most gamma rays. 2357000200025 MONITOR (92-U-235(N,F)MASS,CHN,FY) 2357000200026 From W.Seelmann-Eggebert,G.Pfennig,H.Muenzel, 2357000200027 Chart of the nuclides, Gersbach & Sohn Verlag, 2357000200028 Muenchen, 1968. 2357000200029 MISC-COL (MISC) Number of measurements. 2357000200030 ANALYSIS Pa-231 mass yields were measured relative to U-235 2357000200031 yields and then were normalized to 200 %. 2357000200032 REL-REF (A,30950004,M.N.Namboodiri+,J,JIN,30,2305,1968) 2357000200033 Most agree. 2357000200034 ERR-ANALYS (DATA-ERR) Mean square deviation 2357000200035 STATUS (TABLE) Table 2 of Radiochimica Acta,v.13,p.181,1970, 2357000200036 monitor data from Table 3. 2357000200037 ENDBIB 35 0 2357000200038 COMMON 1 3 2357000200039 EN-DUMMY 2357000200040 EV 2357000200041 1. 2357000200042 ENDCOMMON 3 0 2357000200043 DATA 6 17 2357000200044 MASS DATA DATA-ERR DECAY-FLAG MISC MONIT 2357000200045 NO-DIM PC/FIS PC/FIS NO-DIM NO-DIM PC/FIS 2357000200046 85. 4.423 0.130 1. 4. 1.31 2357000200047 91. 7.196 0.138 2. 9. 5.97 2357000200048 95. 6.373 0.034 3. 56. 6.55 2357000200049 97. 4.599 0.088 4. 20. 6.33 2357000200050 99. 2.512 0.029 5. 54. 6.25 2357000200051 103. 0.386 0.005 6. 32. 2.9 2357000200052 131. 2.625 0.034 7. 40. 2.93 2357000200053 132. 3.494 0.015 8. 49. 4.38 2357000200054 133. 5.045 0.065 9. 42. 6.62 2357000200055 135. 6.617 0.103 10. 12. 6.45 2357000200056 137. 6.964 0.156 11. 5. 6.17 2357000200057 140. 6.976 0.042 12. 67. 6.26 2357000200058 141. 6.789 0.080 13. 25. 5.73 2357000200059 143. 5.043 0.065 14. 29. 5.71 2357000200060 144. 4.659 0.135 15. 12. 5.30 2357000200061 147. 1.808 0.036 16. 26. 2.16 2357000200062 149. 0.914 0.028 17. 21. 1.02 2357000200063 ENDDATA 19 0 2357000200064 ENDSUBENT 63 0 2357000299999 ENDENTRY 2 0 2357099999999