ENTRY 21571 20160907 22522157100000001 SUBENT 21571001 20160907 22522157100100001 BIB 14 31 2157100100002 INSTITUTE (2GERMUN) 2157100100003 REFERENCE (J,NIM,165,565,1979) 2157100100004 AUTHOR (J.I.Kim,R.Beck,E.M.Gryntakis,R.Zaghloul) 2157100100005 TITLE Absolute neutron flux measurements and determination 2157100100006 of the undisturbed resonance integral of the 2157100100007 239Pu(n,f)-reaction with a solid state fission counter2157100100008 FACILITY (REAC,2GERMUN) FRM-reactor of Munich. 2157100100009 SAMPLE The samples of U-233 and Pu-239 as thick as 2157100100010 10-30 mg/cm**2 are prepared by molecular electoplating2157100100011 techniques from organic solutions on Al-foils. 2157100100012 The effective surface of the fissile material on 2157100100013 the target was about 80 mm**2. 2157100100014 INC-SPECT Neutron flux was about 2 x 10**7 n/cm2/s 2157100100015 METHOD (ASSOP) Counting of alpha particles and fission 2157100100016 fragments. 2157100100017 DETECTOR (SIBAR) Surface barrier counter with 100 micro- 2157100100018 meters depleted depth and 100 mm diameter. The 2157100100019 detector was placing in a home made vacuum chamber. 2157100100020 ANALYSIS By measurements of the relative alpha desintegra- 2157100100021 tion rate and fission reaction rate of the target 2157100100022 and monitor nuclide with the fission counter, the 2157100100023 effective cross section of the Pu-239(n,f)-reaction 2157100100024 was determined by using the Westcott convention. 2157100100025 MONITOR (79-AU-197(N,G)79-AU-198,,RI) Resonance 2157100100026 integral including the 1/v part. 2157100100027 CORRECTION .For the scattering and self absorption effects. 2157100100028 ERR-ANALYS (ERR-S) Average statistical errors. 2157100100029 HISTORY (19800408C) 2157100100030 (19800729A) COMMON-section corrected. 2157100100031 (20160907A) SD:Updated to new date formats,lower case. 2157100100032 SF4=Au-198-G+M -> Au-198, SF6=RI/SUM -> RI in MONITOR. 2157100100033 ENDBIB 31 0 2157100100034 COMMON 3 3 2157100100035 EN-NRM-MIN MONIT MONIT-ERR 2157100100036 EV B B 2157100100037 0.5 1551. 12. 2157100100038 ENDCOMMON 3 0 2157100100039 ENDSUBENT 38 0 2157100199999 SUBENT 21571002 20160907 22522157100200001 BIB 2 2 2157100200002 REACTION (94-PU-239(N,F),,RI,,RV) Excess resonance integral 2157100200003 STATUS (TABLE) Value from p.569 of NIM,165(1979)565. 2157100200004 ENDBIB 2 0 2157100200005 NOCOMMON 0 0 2157100200006 DATA 3 1 2157100200007 EN-MIN DATA ERR-S 2157100200008 EV B B 2157100200009 0.15 2156. 57. 2157100200010 ENDDATA 3 0 2157100200011 ENDSUBENT 10 0 2157100299999 ENDENTRY 2 0 2157199999999