ENTRY 21217 19801105 00002121700000001 SUBENT 21217001 19801105 00002121700100001 BIB 13 41 2121700100002 INSTITUTE (2UK HAR) 2121700100003 REFERENCE (C,78HARWELL,337,7809) MAIN REFERENCE. 2121700100004 (P,AERE-PR/NP-25,10,7806) 2121700100005 (P,NEANDC(E)-192,8,7806) 2121700100006 AUTHOR (T.J.HASTE,M.C.MOXON) 2121700100007 TITLE -RESONANCE PARAMETERS OF U-238 BELOW A NEUTRON 2121700100008 ENERGY OF 520 EV-. 2121700100009 FACILITY (LINAC) THE HARWELL 45 MEV ELECTRON LINAC. 2121700100010 INC-SOURCE .THE BOOSTER TARGET AT THE LINAC. 2121700100011 SAMPLE .THREE CONCENTRATIONS OF URANYL NITRATE SOLUTION 2121700100012 IN HEAVY WATER WITH THICKNESSES 0.0761E-3 ATOMS/BARN, 2121700100013 0.1500E-3 ATOMS/BARN AND 0.3037E-3 ATOMS/BARN. 2121700100014 .ONE URANIUM METAL SAMPLE OF THICKNESS 0.4245 2121700100015 ATOMS/BARN. 2121700100016 .URANIUM DIOXIDE SAMPLES WHERE THE THICKNESSES RANGED 2121700100017 FROM 0.0238 TO 0.1416 ATOMS U-238/BARN, (DEPLETED 2121700100018 URANIUM SAMPLES). 2121700100019 METHOD (TOF ) TIME OF FLIGHT AT THE 14 METER AND THE 40 2121700100020 METER FLIGHT PATH. THE ENERGY SCALE WAS ESTABLISHED 2121700100021 USING RESONANCES PRESENT IN THE FILTER MATERIALS OF 2121700100022 TANTALUM, MANGANESE AND ALUMINIUM, WHOSE RESONANCE 2121700100023 ENERGIES WERE ASSUMED FROM THE EVALUATION OF BNL-325 2121700100024 (1973). 2121700100025 DETECTOR (SCIN ) LITHIUM GLASS SCINTILLATOR DETECTORS. 2121700100026 ANALYSIS (MLA ) THE CODE REFIT USING R-MATRIX MULTI-LEVEL 2121700100027 FORMALISM TO DESCRIBE THE NUCLEAR CROSS-SECTION HAVE 2121700100028 BEEN USED. 2121700100029 .DOPPLER BROADENING OF THE CROSS SECTIONS IS CARRIED 2121700100030 OUT USING THE IDEAL GAS MODEL. 2121700100031 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2121700100032 HISTORY (791217C) CN. 2121700100033 (800115E) 2121700100034 (800227A) REACTION STRINGS CORRECTED. 2121700100035 (800303E) 2121700100036 ERR-ANALYS (DATA-ERR) THE QUOTED ERRORS ARE ONE STANDARD 2121700100037 DEVIATION AND ARE STATISTICAL UNCERTAINTIES OBTAINED 2121700100038 FROM FITS TO THE DATA. A QUADRATIC SUM OF THE CO- 2121700100039 VARIANCE TERMS IN THE UNCERTAINTY MATRIX BETWEEN THE 2121700100040 PARAMETERS FITTED ARE BETWEEN ONCE AND TWICE THE 2121700100041 STATISTICAL ERROR. AUTHOR WILL MAKE FUTHER INVESTI- 2121700100042 GATION. 2121700100043 ENDBIB 41 0 2121700100044 NOCOMMON 0 0 2121700100045 ENDSUBENT 44 0 2121700199999 SUBENT 21217002 19801105 00002121700200001 BIB 6 21 2121700200002 REACTION 1(92-U-238(N,EL),,WID) 2121700200003 2(92-U-238(N,G),,WID) 2121700200004 METHOD .THE RADIATION WIDTHS OF THE FOUR LOWEST ENERGY S- 2121700200005 WAVE RESONANCES WERE FITTED USING THE NEUTRON WIDTHS 2121700200006 OBTAINED FROM THE THIN SAMPLE DATA. 2121700200007 ASSUMED (ASSUM,92-U-238(N,G),,WID) ASSUMED DATA 2121700200008 WERE TAKEN FROM EVALUATED DATA,IF NOTHING ELSE 2121700200009 IS STATED. 2121700200010 FLAG (1.) WEIGHTED MEAN VALUES FROM URANIUM OXIDE DATA 2121700200011 AND THIN SAMPLE DATA, AND ASSUMED VALUE FOR 2121700200012 RADIATION WIDTH TAKEN FROM EARLIER CAPTURE 2121700200013 MEASUREMENTS BY AUTHOR. 2121700200014 (2.) NEUTRON WIDTH OBTAINED FROM FITS TO THE URANIUM 2121700200015 OXIDE DATA. 2121700200016 (3.) NEUTRON WIDTH OBTAINED FROM FITS TO THE URANIUM 2121700200017 OXIDE DATA AND ASSUMED VALUE FOR RADIATION WIDTH 2121700200018 TAKEN FROM EARLIER CAPTURE MEASUREMENTS BY 2121700200019 AUTHOR. 2121700200020 STATUS .TABLE 1 IN MAIN REFERENCE. 2121700200021 HISTORY (791217C) 2121700200022 (800227A) 2121700200023 ENDBIB 21 0 2121700200024 COMMON 1 3 2121700200025 MOMENTUM L 2121700200026 NO-DIM 2121700200027 0.0000E+00 2121700200028 ENDCOMMON 3 0 2121700200029 DATA 8 23 2121700200030 EN-RES EN-RES-ERR DATA 1DATA-ERR 1DATA 2DATA-ERR 22121700200031 ASSUM FLAG 2121700200032 EV EV MILLI-EV MILLI-EV MILLI-EV MILLI-EV 2121700200033 MILLI-EV NO-DIM 2121700200034 6.6680E+00 3.0000E-04 1.5070E+00 8.0000E-03 2.3540E+01 5.3000E-012121700200035 2121700200036 2.0877E+01 8.0000E-04 1.0170E+01 1.0000E-01 2.2440E+01 4.3000E-012121700200037 2121700200038 3.6692E+01 1.3000E-03 3.4410E+01 4.1000E-01 2.4030E+01 8.7000E-012121700200039 2121700200040 6.6056E+01 1.7700E-02 2.5640E+01 6.6000E-01 2.3460E+01 5.0000E-012121700200041 2121700200042 8.0762E+01 4.8000E-03 1.7940E+00 5.8000E-02 2121700200043 2.4000E+01 2.0000E+00 2121700200044 1.0259E+02 6.7000E-03 6.9730E+01 5.2000E-01 2121700200045 2.4700E+01 1.0000E+00 2121700200046 1.1693E+02 5.4000E-02 2.5180E+01 1.8000E-01 2121700200047 2.3000E+01 3.0000E+00 2121700200048 1.4556E+02 1.9000E-02 8.1400E-01 5.2000E-02 2121700200049 2.3500E+01 2.0000E+00 2121700200050 1.6519E+02 1.3000E-02 2.9310E+00 1.5700E-01 2121700200051 2.3500E+01 2.0000E+00 2121700200052 1.8979E+02 2.0000E-02 1.8363E+02 1.4900E+00 2121700200053 2.3400E+01 1.0000E+00 2121700200054 2.0852E+02 1.5000E-02 4.9120E+01 1.1600E+00 2121700200055 2.1500E+01 3.0000E+00 2121700200056 2.3718E+02 1.7000E-02 2.6070E+01 8.0000E-01 2121700200057 2.3500E+01 2.0000E+00 2121700200058 2.7351E+02 4.4000E-02 2.3360E+01 1.0500E+00 2121700200059 2.2000E+01 3.0000E+00 2121700200060 2.9077E+02 2.7000E-02 1.4950E+01 9.5000E-01 2121700200061 2.4000E+01 3.0000E+00 2121700200062 3.1113E+02 1.5000E-01 1.2500E+00 3.1000E-01 2121700200063 2.3500E+01 2.0000E+00 2121700200064 3.4756E+02 2.8000E-02 7.4900E+01 1.9000E+00 2121700200065 2.1600E+01 3.0000E+00 2121700200066 3.7626E+02 1.4000E-01 1.4500E+00 2.9000E-01 2121700200067 2.3500E+01 2.0000E+00 2121700200068 3.9732E+02 7.5000E-02 5.9300E+00 3.7000E-01 2121700200069 2.3500E+01 2.0000E+00 2121700200070 4.0990E+02 5.0000E-02 1.8100E+01 1.4000E+00 2121700200071 2.1700E+01 2.0000E+00 2121700200072 4.3369E+02 8.4000E-02 8.7100E+00 1.0700E+00 2121700200073 2.1500E+01 2.0000E+00 2121700200074 4.6275E+02 1.3200E-01 6.1200E+00 7.3000E-01 2121700200075 2.3500E+01 2.0000E+00 2121700200076 4.7790E+02 2.0900E-01 4.0100E+00 5.8000E-01 2121700200077 2.3500E+01 2.0000E+00 2121700200078 5.1804E+02 5.9000E-02 4.7900E+01 2.6000E+00 2121700200079 2.3500E+01 2.0000E+00 2121700200080 ENDDATA 50 0 2121700200081 ENDSUBENT 80 0 2121700299999 SUBENT 21217003 19800303 00002121700300001 BIB 5 9 2121700300002 REACTION (92-U-238(N,EL),,WID,,G) 2121700300003 ASSUMED (ASSUM,92-U-238(N,G),,WID) 2121700300004 FLAG (1.) DATA OBTAINED FROM RUN WITH URANIUM METAL 2121700300005 SAMPLE. 2121700300006 (2.) DATA OBTAINED FROM RUN WITH URANIUM OXIDE 2121700300007 SAMPLE. 2121700300008 STATUS .TABLE 2 IN MAIN REFERENCE. 2121700300009 HISTORY (791217C) 2121700300010 (800227A) 2121700300011 ENDBIB 9 0 2121700300012 COMMON 2 3 2121700300013 MOMENTUM L ASSUM 2121700300014 NO-DIM MILLI-EV 2121700300015 1.0000E+00 2.4000E+01 2121700300016 ENDCOMMON 3 0 2121700300017 DATA 5 5 2121700300018 EN-RES EN-RES-ERR DATA DATA-ERR FLAG 2121700300019 EV EV MILLI-EV MILLI-EV NO-DIM 2121700300020 4.4178E+00 4.2000E-03 1.2300E-04 1.4000E-05 1.0000E+00 2121700300021 1.0240E+01 2.0000E-03 1.5900E-03 6.6000E-05 1.0000E+00 2121700300022 1.1310E+01 7.6000E-03 4.3700E-04 4.3000E-05 1.0000E+00 2121700300023 1.9559E+01 9.7000E-03 1.1300E-03 2.2000E-04 1.0000E+00 2121700300024 8.9217E+01 4.5800E-02 8.4700E-02 5.1000E-04 2.0000E+00 2121700300025 ENDDATA 7 0 2121700300026 ENDSUBENT 25 0 2121700399999 ENDENTRY 3 0 2121799999999