ENTRY 20467 19840120 00002046700000001 SUBENT 20467001 19840120 00002046700100001 BIB 15 41 2046700100002 INSTITUTE (2UK HAR) 2046700100003 REFERENCE (J,NP/A,139,471,6912) 2046700100004 (R,AERE-R-6039,6907) SAME AS ABOVE. 2046700100005 AUTHOR (G.D.JAMES, G.G.SLAUGHTER) 2046700100006 TITLE -THE TOTAL CROSS SECTION OF 92-U-234 AND THE PARAMETERS2046700100007 OF ITS SUB-THRESHOLD FISSION RESONANCES.- 2046700100008 FACILITY (LINAC) 45 MEV HARWELL ELECTRON LINEAR ACCELERATOR. 2046700100009 INC-SOURCE (PHOTO) PHOTO NEUTRONS FROM BOOSTER TARGET. 2046700100010 SAMPLE .OXIDE SAMPLE. 2046700100011 .THREE U-234 OXIDE SAMPLES DOUBLY CANNED IN 2046700100012 CYLINDRICAL BRASS CAPSULES WITH AL FILTERS + END CAPS.2046700100013 .SAMPLE * WEIGHT OF U-234 * SAMPLE DIA.* THICKNESS 2046700100014 1 * 315 MG * 0.635 CM * 0.00258 ATOM/B 2046700100015 2 * 762 MG * 0.635 CM * 0.00619 ATOM/B 2046700100016 3 * 762 MG * 0.386 CM * 0.01674 ATOM/B 2046700100017 99.37 PER CENT 92-U-234, 2046700100018 0.34 PER CENT 92-U-235. 2046700100019 METHOD (TOF ) TIME OF FLIGHT, PATH LENGTH = 14.646 M, 2046700100020 TIMING CHANNEL WIDTH = 125 NS. 2046700100021 ANGLE OF FLIGHT PATH TO MODERATOR NORMAL IS 10 DEG. 2046700100022 DETECTOR (SCIN ) LITHIUM GLASS SCINTILLATOR, TYPE NE 905, 2046700100023 DIAMETER = 1.3 CM, THICKNESS = 1.3 CM, 2046700100024 LITHIUM CONCENTRATION = 7.3 PER CENT, 2046700100025 ENRICHMENT OF LI-6 = 96 PER CENT. 2046700100026 THE SCINTILLATOR WAS MOUNTED ON AN EMI 9524B PHOTO- 2046700100027 MULTIPLIER, AND PULSES VIA AMP.ARE TAKEN TO AERE-1680A2046700100028 MAGNETIC TAPE TOF ANALYZER WITH 8192 TIMING CHANNELS. 2046700100029 PART-DET (N ) NEUTRONS. 2046700100030 ANALYSIS (AREA ) AREA ANALYSIS BY HUGHES, J.NUCL.ENERGY 1(55)2046700100031 237. BUT REVISED CURVES USED. M.C.MOXON,PRIVATE COM. 2046700100032 MONITOR .TRANSMISSION EXPERIMENT. 2046700100033 CORRECTION .BACKGROUND SUBTRACTED USING BLACK SAMPLE MEASUREMENT. 2046700100034 .NEUTRON-BG IS DESCRIBED BY A TIME INDEPENDENT COMPO- 2046700100035 NENT WHICH IS LINEAR ON A DOUBLE LOGARITHMIC GRAPH OF 2046700100036 NEUTRON COUNTS PER TIMING CHANNEL AGAINST NEUTRON 2046700100037 ENERGY. 2046700100038 COMMENT NOTE- IN SPITE OF THE PUBLICATION TITLE THE TOTAL 2046700100039 X-SECT. DATA ARE NOT GIVEN IN THE REFERENCE. 2046700100040 THEY SHOULD BE PUBLISHED LATER IN AN AERE REPORT2046700100041 HISTORY (701119C) 2046700100042 (760112E) 2046700100043 ENDBIB 41 0 2046700100044 NOCOMMON 0 0 2046700100045 ENDSUBENT 44 0 2046700199999 SUBENT 20467002 19840120 00002046700200001 BIB 5 21 2046700200002 REACTION (92-U-234(N,EL),,WID) 2046700200003 STATUS .NUCL.PHYS.,A139,P475 (TABLE 2). 2046700200004 HISTORY (701119C) 2046700200005 (760112E) 2046700200006 CORRECTION .IN THE DETERMINATION OF RESONANCE PARAMETERS FROM A 2046700200007 COMBINATION OF THE RESULTS FROM TWO INDEPENDENT 2046700200008 EXPERIMENTS (FISSION AND TOTAL CROSS-SECTION), IT IS 2046700200009 ESSENTIAL THAT THE E(N) SCALE IN THE TWO EXPERIMENTS 2046700200010 AGREE. THE ENERGY SCALE BY JAMES AND RAE,(NUCL.PHYS. 2046700200011 A118,(68)313) IS INCORRECT AT HIGH ENERGY AND A NEW 2046700200012 SCALE HAS BEEN ADOPTED WHICH IS CORRECT FOR ALUMINIUM 2046700200013 RESONANCE AT 35.4 KEV WHILE MAINTAINING U-234 2046700200014 RESONANCE AT 5.19 EV. 2046700200015 ERR-ANALYS .TO DETERMINE THE NEUTRON WIDTHS, THE RESULTS FROM 3 2046700200016 SAMPLE THICKNESSES WERE ANALYSED INDEPENDENTLY BY AREA2046700200017 METHOD. THE SPREAD OF THE RESULTS FROM THE THREE 2046700200018 THICKNESSES IS TAKEN AS A MEASURE OF THE ERROR IN THE 2046700200019 MEAN VALUE OF NEUTRON WIDTH. 2046700200020 TWO VALUES OF GAMMA-N ARE GIVEN FOR THE 638.4 EV AND 2046700200021 686.7 EV LEVELS. SEE TEXT, PAG. 474. 2046700200022 GAMMA-N FOR THE 722.0 EV LEVEL COULD NOT BE DETERMINED2046700200023 ENDBIB 21 0 2046700200024 NOCOMMON 0 0 2046700200025 DATA 4 40 2046700200026 EN-RES DATA +DATA-ERR -DATA-ERR 2046700200027 EV MILLI-EV MILLI-EV MILLI-EV 2046700200028 5.1900E+00 3.9200E+00 1.9000E-02 1.9000E-02 2046700200029 2.2740E+01 1.8000E-02 2.0000E-03 2.0000E-03 2046700200030 2.3420E+01 1.6000E-01 2.0000E-02 2.0000E-02 2046700200031 3.1210E+01 6.5000E+00 2.5000E-01 2.5000E-01 2046700200032 3.6860E+01 5.8000E-02 5.0000E-03 5.0000E-03 2046700200033 4.5830E+01 2.9700E-01 1.4000E-02 1.4000E-02 2046700200034 4.8750E+01 8.0000E+00 7.0000E-01 7.0000E-01 2046700200035 7.7660E+01 7.9000E+00 3.0000E-01 3.0000E-01 2046700200036 9.4750E+01 4.1000E+01 2.0000E+00 2.0000E+00 2046700200037 1.0665E+02 3.2000E+00 3.0000E-01 3.0000E-01 2046700200038 1.1149E+02 1.7800E+01 6.0000E-01 6.0000E-01 2046700200039 1.4675E+02 8.7000E+00 1.4000E+00 1.4000E+00 2046700200040 1.5281E+02 1.9700E+01 6.0000E-01 6.0000E-01 2046700200041 1.7725E+02 2.8000E+01 4.0000E+00 4.0000E+00 2046700200042 1.8350E+02 4.0000E+01 6.0000E+00 6.0000E+00 2046700200043 1.8830E+02 5.2000E+01 1.0000E+00 1.0000E+00 2046700200044 2.0950E+02 6.4000E+00 1.5000E+00 1.5000E+00 2046700200045 2.3870E+02 3.9000E+00 8.0000E-01 8.0000E-01 2046700200046 2.5910E+02 7.0000E+00 1.4000E+00 1.4000E+00 2046700200047 2.7780E+02 3.2000E+00 3.0000E-01 3.0000E-01 2046700200048 2.9140E+02 2.9000E+01 2.0000E+00 2.0000E+00 2046700200049 3.0980E+02 1.1300E+01 1.2000E+00 1.2000E+00 2046700200050 3.2450E+02 1.6200E+01 4.0000E-01 4.0000E-01 2046700200051 3.3290E+02 2.7000E+00 2.0000E-01 2.0000E-01 2046700200052 3.5080E+02 2.7000E+01 6.0000E+00 6.0000E+00 2046700200053 3.6030E+02 3.7000E+01 5.0000E+00 5.0000E+00 2046700200054 3.9310E+02 1.0000E+01 1.5000E+00 1.5000E+00 2046700200055 4.1410E+02 4.1000E+00 1.0000E-01 1.0000E-01 2046700200056 4.3910E+02 2.2000E+00 8.0000E-01 8.0000E-01 2046700200057 4.5700E+02 1.0000E+01 1.7000E+00 1.7000E+00 2046700200058 4.6640E+02 1.2500E+01 1.6000E+00 1.6000E+00 2046700200059 4.9110E+02 3.6000E+01 1.1000E+01 1.1000E+01 2046700200060 5.1500E+02 7.0000E+01 3.0000E+01 3.0000E+01 2046700200061 5.4980E+02 4.7000E+01 1.3000E+01 1.3000E+01 2046700200062 5.5910E+02 7.2000E+01 2.6000E+01 2.6000E+01 2046700200063 5.7830E+02 4.4000E+01 1.0000E+01 1.0000E+01 2046700200064 6.3840E+02 2.0000E+00 8.0000E+00 7.0000E-01 2046700200065 6.8670E+02 1.2000E+01 8.0000E+00 8.0000E+00 2046700200066 7.7000E+02 7.1000E+02 8.5000E+01 8.5000E+01 2046700200067 8.1760E+02 2.6000E+02 1.0000E+02 1.0000E+02 2046700200068 ENDDATA 42 0 2046700200069 ENDSUBENT 68 0 2046700299999 SUBENT 20467003 19840120 00002046700300001 BIB 5 26 2046700300002 REACTION (92-U-234(N,F),,WID) 2046700300003 STATUS .NUCL.PHYS.,A139,P475 (TABLE 2). 2046700300004 HISTORY (701119C) 2046700300005 (760112E) 2046700300006 CORRECTION .IN THE DETERMINATION OF RESONANCE PARAMETERS FROM A 2046700300007 COMBINATION OF THE RESULTS FROM TWO INDEPENDENT 2046700300008 EXPERIMENTS (FISSION AND TOTAL CROSS-SECTION), IT IS 2046700300009 ESSENTIAL THAT THE E(N) SCALE IN THE TWO EXPERIMENTS 2046700300010 AGREE. THE ENERGY SCALE BY JAMES AND RAE,(NUCL.PHYS. 2046700300011 A118,(68)313) IS INCORRECT AT HIGH ENERGY AND A NEW 2046700300012 SCALE HAS BEEN ADOPTED WHICH IS CORRECT FOR ALUMINIUM 2046700300013 RESONANCE AT 35.4 KEV WHILE MAINTAINING U-234 2046700300014 RESONANCE AT 5.19 EV. 2046700300015 ERR-ANALYS .THE FISSION WIDTH DEDUCED FOR AN ASSUMED CONST-VALUE 2046700300016 OF RADIATION WIDTH = 25 MILLI-EV. 2046700300017 .FISSION WIDTHS COULD BE OBTAINED FOR 38 LEVELS BELOW 2046700300018 686.7 EV. EXCEPT LAST TWO OF THESE LEVELS IT WAS 2046700300019 POSSIBLE TO REDUCE THE ERROR IN FISSION WIDTH FROM THE2046700300020 ERRORS IN NEUTRON WIDTH AND SIGZERO*G(F). BUT FOR THE 2046700300021 TWO LEVELS AT 638.4 EV AND 686.7 EV THE LOWER LIMIT TO2046700300022 G(N) IS ZERO AND THIS DOES NOT GIVE AN UPPER BOUND TO 2046700300023 G(F). IN THESE TWO CASES, THE UPPER LIMIT TO G(F) IS 2046700300024 TAKEN AS THE OBSERVED RESONANCE WIDTH MINUS THE WIDTH 2046700300025 OF RESOLUTION FUNCTION CALCULATED. 2046700300026 TWO VALUES OF GAMMA-F ARE GIVEN FOR THE 638.4 EV AND 2046700300027 686.7 EV LEVELS. 2046700300028 ENDBIB 26 0 2046700300029 NOCOMMON 0 0 2046700300030 DATA 4 38 2046700300031 EN-RES DATA +DATA-ERR -DATA-ERR 2046700300032 EV MILLI-EV MILLI-EV MILLI-EV 2046700300033 5.1900E+00 1.9000E-02 1.0000E-03 1.0000E-03 2046700300034 2.2740E+01-3.7000E-02 1.3400E-01 1.3400E-01 2046700300035 2.3420E+01-1.3000E-02 1.6000E-02 1.6000E-02 2046700300036 3.1210E+01 1.2000E-02 1.0000E-03 1.0000E-03 2046700300037 3.6860E+01-8.0000E-02 1.4200E-01 1.4200E-01 2046700300038 4.5830E+01 1.0800E-01 3.9000E-02 3.9000E-02 2046700300039 4.8750E+01 4.0000E-03 2.0000E-03 2.0000E-03 2046700300040 7.7660E+01 1.1000E-02 5.0000E-03 5.0000E-03 2046700300041 9.4750E+01 4.0000E-02 5.0000E-03 5.0000E-03 2046700300042 1.0665E+02 1.1000E-01 2.9000E-02 2.9000E-02 2046700300043 1.1149E+02 2.9700E-01 2.4000E-02 2.4000E-02 2046700300044 1.4675E+02 7.0000E-03 1.6000E-02 1.6000E-02 2046700300045 1.5281E+02 2.3000E-02 9.0000E-03 9.0000E-03 2046700300046 1.7725E+02 1.2000E-01 1.7000E-02 1.7000E-02 2046700300047 1.8350E+02 1.3300E-01 1.7000E-02 1.7000E-02 2046700300048 1.8830E+02 3.2000E-02 1.0000E-02 1.0000E-02 2046700300049 2.0950E+02 2.0000E-03 3.0000E-02 3.0000E-02 2046700300050 2.3870E+02 9.1000E-02 6.3000E-02 6.3000E-02 2046700300051 2.5910E+02 4.2200E-01 8.0000E-02 8.0000E-02 2046700300052 2.7780E+02 2.1600E-01 1.0100E-01 1.0100E-01 2046700300053 2.9140E+02 2.0900E-01 3.2000E-02 3.2000E-02 2046700300054 3.0980E+02 1.2700E-01 5.4000E-02 5.4000E-02 2046700300055 3.2450E+02 1.7000E-02 3.9000E-02 3.9000E-02 2046700300056 3.3290E+02 1.6600E-01 1.4300E-01 1.4300E-01 2046700300057 3.5080E+02 1.7300E-01 5.3000E-02 5.3000E-02 2046700300058 3.6030E+02 0.0000E+00 4.9000E-02 4.9000E-02 2046700300059 3.9310E+02 7.1100E-01 1.3800E-01 1.3800E-01 2046700300060 4.1410E+02 6.6700E-01 2.3200E-01 2.3200E-01 2046700300061 4.3910E+02 1.2290E+00 4.4300E-01 4.4300E-01 2046700300062 4.5700E+02 9.3200E+00 9.2400E-01 9.2400E-01 2046700300063 4.6640E+02 3.1300E-01 1.9700E-01 1.9700E-01 2046700300064 4.9110E+02 1.6690E+00 1.6400E-01 1.6400E-01 2046700300065 5.1500E+02 5.0530E+00 4.0600E-01 4.0600E-01 2046700300066 5.4980E+02 0.0000E+00 1.6000E-01 1.6000E-01 2046700300067 5.5910E+02 5.6400E+00 4.5400E-01 4.5400E-01 2046700300068 5.7830E+02 5.3670E+00 4.5200E-01 4.5200E-01 2046700300069 6.3840E+02 5.1100E+01 7.0000E+02 1.6200E+01 2046700300070 6.8670E+02 9.0600E+00 5.0000E+02 8.4000E-01 2046700300071 ENDDATA 40 0 2046700300072 ENDSUBENT 71 0 2046700399999 SUBENT 20467004 19840120 00002046700400001 BIB 5 24 2046700400002 REACTION (92-U-234(N,F),,WID,,S0) 2046700400003 STATUS .NUCL.PHYS.,A139,P475 (TABLE 2). 2046700400004 HISTORY (701119C) 2046700400005 (760112E) 2046700400006 CORRECTION .IN THE DETERMINATION OF RESONANCE PARAMETERS FROM A 2046700400007 COMBINATION OF THE RESULTS FROM TWO INDEPENDENT 2046700400008 EXPERIMENTS (FISSION AND TOTAL CROSS-SECTION), IT IS 2046700400009 ESSENTIAL THAT THE E(N) SCALE IN THE TWO EXPERIMENTS 2046700400010 AGREE. THE ENERGY SCALE BY JAMES AND RAE,(NUCL.PHYS. 2046700400011 A118,(68)313) IS INCORRECT AT HIGH ENERGY AND A NEW 2046700400012 SCALE HAS BEEN ADOPTED WHICH IS CORRECT FOR ALUMINIUM 2046700400013 RESONANCE AT 35.4 KEV WHILE MAINTAINING U-234 2046700400014 RESONANCE AT 5.19 EV. 2046700400015 ERR-ANALYS .THE FISSION WIDTH DEDUCED FOR AN ASSUMED CONST-VALUE 2046700400016 OF RADIATION WIDTH = 25 MILLI-EV. 2046700400017 .FISSION WIDTHS COULD BE OBTAINED FOR 38 LEVELS BELOW 2046700400018 686.7 EV. EXCEPT LAST TWO OF THESE LEVELS IT WAS 2046700400019 POSSIBLE TO REDUCE THE ERROR IN FISSION WIDTH FROM THE2046700400020 ERRORS IN NEUTRON WIDTH AND SIGZERO*G(F). BUT FOR THE 2046700400021 TWO LEVELS AT 638.4 EV AND 686.7 EV THE LOWER LIMIT TO2046700400022 G(N) IS ZERO AND THIS DOES NOT GIVE AN UPPER BOUND TO 2046700400023 G(F). IN THESE TWO CASES, THE UPPER LIMIT TO G(F) IS 2046700400024 TAKEN AS THE OBSERVED RESONANCE WIDTH MINUS THE WIDTH 2046700400025 OF RESOLUTION FUNCTION CALCULATED. 2046700400026 ENDBIB 24 0 2046700400027 NOCOMMON 0 0 2046700400028 DATA 3 39 2046700400029 EN-RES DATA DATA-ERR 2046700400030 EV B*EV B*EV 2046700400031 5.1900E+00 1.2500E+00 8.5000E-02 2046700400032 2.2740E+01-3.0000E-03 1.1000E-02 2046700400033 2.3420E+01-9.0000E-03 1.1000E-02 2046700400034 3.1210E+01 2.0400E-01 2.5000E-02 2046700400035 3.6860E+01-1.3000E-02 2.3000E-02 2046700400036 4.5830E+01 7.1000E-02 2.6000E-02 2046700400037 4.8750E+01 5.0000E-02 3.0000E-02 2046700400038 7.7660E+01 9.1000E-02 4.7000E-02 2046700400039 9.4750E+01 6.8300E-01 8.7000E-02 2046700400040 1.0665E+02 3.0200E-01 8.0000E-02 2046700400041 1.1149E+02 2.8500E+00 2.3000E-01 2046700400042 1.4675E+02 3.1000E-02 7.1000E-02 2046700400043 1.5281E+02 1.7500E-01 7.0000E-02 2046700400044 1.7725E+02 9.2000E-01 1.3000E-01 2046700400045 1.8350E+02 1.1500E+00 1.5000E-01 2046700400046 1.8830E+02 2.9700E-01 9.7000E-02 2046700400047 2.0950E+02 6.0000E-03 7.6000E-02 2046700400048 2.3870E+02 1.3200E-01 9.2000E-02 2046700400049 2.5910E+02 9.1000E-01 1.7000E-01 2046700400050 2.7780E+02 2.2600E-01 1.0500E-01 2046700400051 2.9140E+02 9.9000E-01 1.5000E-01 2046700400052 3.0980E+02 3.3000E-01 1.4000E-01 2046700400053 3.2450E+02 5.2000E-02 1.2200E-01 2046700400054 3.3290E+02 1.2500E-01 1.0700E-01 2046700400055 3.5080E+02 6.6000E-01 2.0000E-01 2046700400056 3.6030E+02 0.0000E+00 2.1000E-01 2046700400057 3.9310E+02 1.3100E+00 2.5000E-01 2046700400058 4.1410E+02 5.7400E-01 1.9500E-01 2046700400059 4.3910E+02 5.6000E-01 1.9300E-01 2046700400060 4.5700E+02 1.1900E+01 9.3000E-01 2046700400061 4.6640E+02 5.7300E-01 3.5000E-01 2046700400062 4.9110E+02 5.0500E+00 4.8000E-01 2046700400063 5.1500E+02 1.7750E+01 1.3200E+00 2046700400064 5.4980E+02 0.0000E+00 5.0000E-01 2046700400065 5.5910E+02 1.8300E+01 1.3600E+00 2046700400066 5.7830E+02 1.4200E+01 1.1000E+00 2046700400067 6.3840E+02 5.3000E+00 5.7000E-01 2046700400068 6.8670E+02 8.8900E+00 7.9000E-01 2046700400069 7.2200E+02 3.8500E+00 5.1000E-01 2046700400070 ENDDATA 41 0 2046700400071 ENDSUBENT 70 0 2046700499999 SUBENT 20467005 19840120 00002046700500001 BIB 5 14 2046700500002 REACTION (92-U-234(N,0),,EN) 2046700500003 CORRECTION .IN THE DETERMINATION OF RESONANCE PARAMETERS FROM A 2046700500004 COMBINATION OF THE RESULTS FROM TWO INDEPENDENT 2046700500005 EXPERIMENTS (FISSION AND TOTAL CROSS-SECTION), IT IS 2046700500006 ESSENTIAL THAT THE E(N) SCALE IN THE TWO EXPERIMENTS 2046700500007 AGREE. THE ENERGY SCALE BY JAMES AND RAE,(NUCL.PHYS. 2046700500008 A118,(68)313) IS INCORRECT AT HIGH ENERGY AND A NEW 2046700500009 SCALE HAS BEEN ADOPTED WHICH IS CORRECT FOR ALUMINIUM 2046700500010 RESONANCE AT 35.4 KEV WHILE MAINTAINING U-234 2046700500011 RESONANCE AT 5.19 EV. 2046700500012 ERR-ANALYS NOT GIVEN. 2046700500013 STATUS .NUCL.PHYS.,A139,P475 (TABLE 2). 2046700500014 HISTORY (701119C) 2046700500015 (760112E) 2046700500016 ENDBIB 14 0 2046700500017 NOCOMMON 0 0 2046700500018 DATA 1 41 2046700500019 DATA 2046700500020 EV 2046700500021 5.1900E+00 2046700500022 2.2740E+01 2046700500023 2.3420E+01 2046700500024 3.1210E+01 2046700500025 3.6860E+01 2046700500026 4.5830E+01 2046700500027 4.8750E+01 2046700500028 7.7660E+01 2046700500029 9.4750E+01 2046700500030 1.0665E+02 2046700500031 1.1149E+02 2046700500032 1.4675E+02 2046700500033 1.5281E+02 2046700500034 1.7725E+02 2046700500035 1.8350E+02 2046700500036 1.8830E+02 2046700500037 2.0950E+02 2046700500038 2.3870E+02 2046700500039 2.5910E+02 2046700500040 2.7780E+02 2046700500041 2.9140E+02 2046700500042 3.0980E+02 2046700500043 3.2450E+02 2046700500044 3.3290E+02 2046700500045 3.5080E+02 2046700500046 3.6030E+02 2046700500047 3.9310E+02 2046700500048 4.1410E+02 2046700500049 4.3910E+02 2046700500050 4.5700E+02 2046700500051 4.6640E+02 2046700500052 4.9110E+02 2046700500053 5.1500E+02 2046700500054 5.4980E+02 2046700500055 5.5910E+02 2046700500056 5.7830E+02 2046700500057 6.3840E+02 2046700500058 6.8670E+02 2046700500059 7.2200E+02 2046700500060 7.7000E+02 2046700500061 8.1760E+02 2046700500062 ENDDATA 43 0 2046700500063 ENDSUBENT 62 0 2046700599999 SUBENT 20467006 19840120 00002046700600001 BIB 5 12 2046700600002 REACTION (92-U-234(N,EL),,STF) 2046700600003 COMMENT MAXIMUM LIKELIHOOD METHOD USED. THE NUMBER OF DEGREE 2046700600004 OF FREEDOM FOR A CHI SQUARE DISTRIBUTION OF THE 2046700600005 REDUCED NEUTRON WIDTHS IS 1.24 +- 0.24. 2046700600006 STATUS .NUCL.PHYS.,A139,P476. 2046700600007 HISTORY (701119C) 2046700600008 (760112E) 2046700600009 ERR-ANALYS .TO DETERMINE THE NEUTRON WIDTHS, THE RESULTS FROM 3 2046700600010 SAMPLE THICKNESSES WERE ANALYSED INDEPENDENTLY BY AREA2046700600011 METHOD. THE SPREAD OF THE RESULTS FROM THE THREE 2046700600012 THICKNESSES IS TAKEN AS A MEASURE OF THE ERROR IN THE 2046700600013 MEAN VALUE OF NEUTRON WIDTH. 2046700600014 ENDBIB 12 0 2046700600015 COMMON 1 3 2046700600016 MOMENTUM L 2046700600017 NO-DIM 2046700600018 0.0000E+00 2046700600019 ENDCOMMON 3 0 2046700600020 DATA 4 1 2046700600021 EN-MAX EN-MIN DATA DATA-ERR 2046700600022 MEV MEV NO-DIM NO-DIM 2046700600023 3.5000E-02 1.0000E-06 1.0900E-04 7.2000E-05 2046700600024 ENDDATA 3 0 2046700600025 ENDSUBENT 24 0 2046700699999 SUBENT 20467007 19840120 00002046700700001 BIB 5 10 2046700700002 REACTION (92-U-234(N,0),,D) 2046700700003 COMMENT LEVEL SPACING GIVEN FROM 17 RESONANCES BELOW 210 EV. 2046700700004 STATUS .NUCL.PHYS.,A139,P476. 2046700700005 HISTORY (701119C) 2046700700006 (760112E) 2046700700007 ERR-ANALYS .TO DETERMINE THE NEUTRON WIDTHS, THE RESULTS FROM 3 2046700700008 SAMPLE THICKNESSES WERE ANALYSED INDEPENDENTLY BY AREA2046700700009 METHOD. THE SPREAD OF THE RESULTS FROM THE THREE 2046700700010 THICKNESSES IS TAKEN AS A MEASURE OF THE ERROR IN THE 2046700700011 MEAN VALUE OF NEUTRON WIDTH. 2046700700012 ENDBIB 10 0 2046700700013 COMMON 1 3 2046700700014 MOMENTUM L 2046700700015 NO-DIM 2046700700016 0.0000E+00 2046700700017 ENDCOMMON 3 0 2046700700018 DATA 4 1 2046700700019 EN-MAX EN-MIN DATA DATA-ERR 2046700700020 MEV MEV EV EV 2046700700021 3.5000E-02 1.0000E-06 1.2300E+01 1.5000E+00 2046700700022 ENDDATA 3 0 2046700700023 ENDSUBENT 22 0 2046700799999 ENDENTRY 7 0 2046799999999