ENTRY 20584 19840126 00002058400000001 SUBENT 20584001 19840126 00002058400100001 BIB 18 42 2058400100002 INSTITUTE (2UK ALD) J.L.PERKIN,P.H.WHITE,P.FIELDHOUSE. 2058400100003 (2UK NPL) E.J.AXTON,P.CROSS,J.C.ROBERTSON. 2058400100004 REFERENCE (J,JNE/AB,19,(6),423,6506) 2058400100005 AUTHOR (J.L.PERKIN,P.H.WHITE,P.FIELDHOUSE,E.J.AXTON,P.CROSS, 2058400100006 J.C.ROBERTSON) 2058400100007 TITLE -THE FISSION CROSS SECTIONS OF U233,U234,U235,U236, 2058400100008 NP237,PU239,PU240 AND PU241 FOR 24 KEV NEUTRONS- 2058400100009 FACILITY .NPL MANGANESE BATH. 2058400100010 .AWRE OIL BATH. 2058400100011 .AERE BORON PILE 2058400100012 INC-SOURCE (PHOTO) BE9(GAMMA,N) REACTION FROM A SPHERICAL 2058400100013 SB-BE SOURCE 2.35 CM DIAMETER. NEUTRON OUTPUT OF 2058400100014 SOURCE = (1012+-5)*10**7 NEUTRONS/SEC. 2058400100015 INC-SPECT .CONTINUOUS,PEAKED AT 24KEV. 2058400100016 SAMPLE .FOILS OF FISSILE MATERIALS,3.18 CM DIAMETER, 2058400100017 DEPOSITED ON PT. 2058400100018 .DETAILS ABOUT ISOTOPIC COMPOSITION,THICKNESS AND 2058400100019 INCERTITUDES OF SAMPLES GIVEN IN TABLE 2 OF 2058400100020 REFERENCE JOUR.NUCL.ENERG.,19,423(1965). 2058400100021 METHOD .DIRECT CALIBRATION OF NEUTRON SOURCE BY MN-BATH, 2058400100022 AND OIL-BATH,INDIRECT CALIBRATION WITH BORON PILE. 2058400100023 DETECTOR (FISCH) FISSION CHAMBER. 2058400100024 ANALYSIS . FORMULA IN P.424 FROM REFERENCE J.NUCL.ENERG. 2058400100025 19 (1965) 423 ACCOUNTING EFFICIENCY OF THE 2058400100026 DETECTION SYSTEM, RESONANCE CAPTURE NEUTRONS AND 2058400100027 SELF-SHIELDING 2058400100028 MONITOR .FISSION CROSS SECTION AT 24 KEV OBTAINED FROM 2058400100029 CROSS-SECTIONS AVERAGED OVER SOURCE SPECTRUM USING 2058400100030 THE GENERAL SHAPE OF THE FISSION CROSS-SECTION 2058400100031 ENERGY DEPENDENCE GIVEN IN SEVERAL REFERENCES, SEE 2058400100032 LIST ON FIG.3 OF JOURN.NUCL.ENERG.,19,423(1965). 2058400100033 PART-DET (FF ) FISSION FRAGMENTS. 2058400100034 COMMENT .COMPARISONS WITH PREVIOUS DATA ARE GIVEN IN GRAPHS. 2058400100035 STATUS .NUMERICAL DATA TAKEN FROM P.423 OF REFERENCE. 2058400100036 HISTORY (760713C) 2058400100037 (761217E) 2058400100038 CORRECTION .SELF-ABSORPTION OF FISSION FRAGMENTS IN SAMPLE. 2058400100039 .EFFECT OF FINITE SIZE OF NEUTRON SOURCE AND SAMPLE. 2058400100040 .SPONTANEOUS FISSION BACKGROUND. 2058400100041 ERR-ANALYS .STATISTICAL ERRORS ARE IN DOMINANCE. 2058400100042 .UNCERTAINTIES OF CORRECTIONS AND SAMPLE COMPOSITION 2058400100043 ACCOUNTED. 2058400100044 ENDBIB 42 0 2058400100045 NOCOMMON 0 0 2058400100046 ENDSUBENT 45 0 2058400199999 SUBENT 20584002 19840126 00002058400200001 BIB 2 3 2058400200002 REACTION (92-U-233(N,F),,SIG) 2058400200003 HISTORY (760713C) 2058400200004 (761217E) 2058400200005 ENDBIB 3 0 2058400200006 NOCOMMON 0 0 2058400200007 DATA 3 1 2058400200008 EN DATA DATA-ERR 2058400200009 KEV B B 2058400200010 2.4000E+01 2.7300E+00 1.1000E-01 2058400200011 ENDDATA 3 0 2058400200012 ENDSUBENT 11 0 2058400299999 SUBENT 20584003 19840126 00002058400300001 BIB 2 3 2058400300002 REACTION (92-U-234(N,F),,SIG) 2058400300003 HISTORY (760713C) 2058400300004 (761217E) 2058400300005 ENDBIB 3 0 2058400300006 NOCOMMON 0 0 2058400300007 DATA 3 1 2058400300008 EN DATA DATA-ERR 2058400300009 KEV B B 2058400300010 2.4000E+01 1.5000E-02 4.0000E-03 2058400300011 ENDDATA 3 0 2058400300012 ENDSUBENT 11 0 2058400399999 SUBENT 20584004 19840126 00002058400400001 BIB 2 3 2058400400002 REACTION (92-U-235(N,F),,SIG) 2058400400003 HISTORY (760713C) 2058400400004 (761217E) 2058400400005 ENDBIB 3 0 2058400400006 NOCOMMON 0 0 2058400400007 DATA 3 1 2058400400008 EN DATA DATA-ERR 2058400400009 KEV B B 2058400400010 2.4000E+01 2.3600E+00 6.0000E-02 2058400400011 ENDDATA 3 0 2058400400012 ENDSUBENT 11 0 2058400499999 SUBENT 20584005 19840126 00002058400500001 BIB 2 3 2058400500002 REACTION (92-U-236(N,F),,SIG) 2058400500003 HISTORY (760713C) 2058400500004 (761217E) 2058400500005 ENDBIB 3 0 2058400500006 NOCOMMON 0 0 2058400500007 DATA 2 1 2058400500008 EN DATA-MAX 2058400500009 KEV B 2058400500010 2.4000E+01 4.0000E-03 2058400500011 ENDDATA 3 0 2058400500012 ENDSUBENT 11 0 2058400599999 SUBENT 20584006 19840126 00002058400600001 BIB 2 3 2058400600002 REACTION (93-NP-237(N,F),,SIG) 2058400600003 HISTORY (760713C) 2058400600004 (761217E) 2058400600005 ENDBIB 3 0 2058400600006 NOCOMMON 0 0 2058400600007 DATA 3 1 2058400600008 EN DATA DATA-ERR 2058400600009 KEV B B 2058400600010 2.4000E+01 1.1000E-02 2.0000E-03 2058400600011 ENDDATA 3 0 2058400600012 ENDSUBENT 11 0 2058400699999 SUBENT 20584007 19840126 00002058400700001 BIB 2 3 2058400700002 REACTION (94-PU-239(N,F),,SIG) 2058400700003 HISTORY (760713C) 2058400700004 (761217E) 2058400700005 ENDBIB 3 0 2058400700006 NOCOMMON 0 0 2058400700007 DATA 3 1 2058400700008 EN DATA DATA-ERR 2058400700009 KEV B B 2058400700010 2.4000E+01 1.6600E+00 7.0000E-02 2058400700011 ENDDATA 3 0 2058400700012 ENDSUBENT 11 0 2058400799999 SUBENT 20584008 19840126 00002058400800001 BIB 2 3 2058400800002 REACTION (94-PU-240(N,F),,SIG) 2058400800003 HISTORY (760713C) 2058400800004 (761217E) 2058400800005 ENDBIB 3 0 2058400800006 NOCOMMON 0 0 2058400800007 DATA 3 1 2058400800008 EN DATA DATA-ERR 2058400800009 KEV B B 2058400800010 2.4000E+01 1.0600E-01 1.8000E-02 2058400800011 ENDDATA 3 0 2058400800012 ENDSUBENT 11 0 2058400899999 SUBENT 20584009 19840126 00002058400900001 BIB 2 3 2058400900002 REACTION (94-PU-241(N,F),,SIG) 2058400900003 HISTORY (760713C) 2058400900004 (761217E) 2058400900005 ENDBIB 3 0 2058400900006 NOCOMMON 0 0 2058400900007 DATA 3 1 2058400900008 EN DATA DATA-ERR 2058400900009 KEV B B 2058400900010 2.4000E+01 2.8300E+00 2.1000E-01 2058400900011 ENDDATA 3 0 2058400900012 ENDSUBENT 11 0 2058400999999 ENDENTRY 9 0 2058499999999