ENTRY 23514 20190603 22802351400000001 SUBENT 23514001 20190603 22802351400100001 BIB 11 43 2351400100002 TITLE Measurement of buckling and relative reaction rates in 2351400100003 some plutonium-graphite assembles 2351400100004 AUTHOR (D.H.Carter,W.G.Clarke,C.Hunt,J.Marshall,D.B.McCulloch,2351400100005 J.E.Sanders,C.R.Symons) 2351400100006 REFERENCE (J,JNE/AB,18,105,1964) 2351400100007 INSTITUTE (2UK WIN) 2351400100008 REL-REF (M,,C.J.Campbell+,C,58GENEVA,15,(P10),1958) 15/P10 2351400100009 Relative fission rates measurement method used is 2351400100010 similar to one of Campbell+ - thermal comparison. 2351400100011 . STEWPOT - 43=group diffusion-theory code (mentioned a2351400100012 "Massimo+, to be published") 2351400100013 INC-SPECT Lattice spectrum and thermal spectrum 2351400100014 DETECTOR (FISCH) 1/8 inch diameter, 4ft 6inch long, operate at 2351400100015 600 deg C temperature, active length 0.4inch. 2351400100016 METHOD Fission rates were determined at the center of 2351400100017 graphite filler. 2351400100018 Thermal calibration before and after experiment. 2351400100019 CORRECTION Absorption of neutrons by the walls of the chambers 2351400100020 - of order 1/3 %. 2351400100021 Self-shielding within the fissile coating of the 2351400100022 chambers was negligible 2351400100023 ADD-RES .Reaction rates ratios measured ( Table 9): 2351400100024 System Temp,K F(Pu239/U235) F(U233/U235) 2351400100025 PuG1 288 1.330+-0.011 1.175+-0.011 2351400100026 PuG2 290 1.554+-0.011 1.395+-0.011 2351400100027 PuG2 473 1.443+-0.029 1.410+-0.022 2351400100028 PuG2 645 1.184+-0.024 1.430+-0.021 2351400100029 PuG3 290 1.520+-0.013 1.350+-0.012 2351400100030 PuG4 291 1.745+-0.017 1.660+-0.015 2351400100031 PuG5 290 1.790+-0.016 1.885+-0.018 2351400100032 UG1 291 1.612+-0.015 1.315+-0.013 2351400100033 Ratios to boron at PuG3 system and 290 deg K: 2351400100034 F(Pu239/B) F(U235/B) F(U233/B) 2351400100035 1.520+-0.018 0.988+-0.018 1.334+-0.016 2351400100036 See Table 1 for Systems used. 2351400100037 . Where 2351400100038 F(i/j)=(Ci/Cj lattice spect.)/(Ci/Cj thermal spect.), 2351400100039 Ci- fission chamber count rate for i= U233,U235,Pu239. 2351400100040 .Reaction rates ratio uncertainty includes 2351400100041 counting statistics, 2351400100042 uncertainty of correction, 2351400100043 inaccuracies in locating the fission chambers 2351400100044 HISTORY (20190604C) M.M. 2351400100045 ENDBIB 43 0 2351400100046 NOCOMMON 0 0 2351400100047 ENDSUBENT 46 0 2351400199999 SUBENT 23514002 20190604 22802351400200001 BIB 4 6 2351400200002 REACTION (94-PU-239(N,ABS),,ETA,,,DERIV) 2351400200003 ANALYSIS Derived from measured buckling and calculated data by 2351400200004 STEWPOT. 2351400200005 ERR-ANALYS (DATA-ERR) One standard deviation 2351400200006 STATUS (TABLE) Text of abstract and text page 120 of 2351400200007 Nucl.Energy,A and B,v.18,p.105,1964 2351400200008 ENDBIB 6 0 2351400200009 NOCOMMON 0 0 2351400200010 DATA 3 1 2351400200011 EN DATA DATA-ERR 2351400200012 EV PRT/REAC PRT/REAC 2351400200013 0.0253 2.11 0.05 2351400200014 ENDDATA 3 0 2351400200015 ENDSUBENT 14 0 2351400299999 SUBENT 23514003 20190604 22802351400300001 BIB 4 6 2351400300002 REACTION ((94-PU-239(N,ABS),,ETA)/(92-U-235(N,ABS),,ETA)) 2351400300003 ANALYSIS Derived from measured data for UG1,PuG2,PuG3 and 2351400300004 spectrum dependence given by the STEWPOT data. 2351400300005 ERR-ANALYS (DATA-ERR) One standard deviation 2351400300006 STATUS (TABLE) Text page 121 of 2351400300007 Nucl.Energy,A and B,v.18,p.105,1964 2351400300008 ENDBIB 6 0 2351400300009 NOCOMMON 0 0 2351400300010 DATA 3 1 2351400300011 EN DATA DATA-ERR 2351400300012 EV NO-DIM NO-DIM 2351400300013 0.0253 1.02 0.02 2351400300014 ENDDATA 3 0 2351400300015 ENDSUBENT 14 0 2351400399999 ENDENTRY 3 0 2351499999999