ENTRY 21207 20060809 21782120700000001 SUBENT 21207001 20060809 21782120700100001 BIB 13 32 2120700100002 INSTITUTE (2UK HAR) AERE HARWELL. 2120700100003 REFERENCE (J,JNE/A,11,34,195911) REVISED VALUE. 2120700100004 (J,PPS/A,65,203,1952) SUPERSEDED. 2120700100005 AUTHOR (D.J.LITTLER) 2120700100006 TITLE -THE RATE OF EMISSION OF SPONTANEOUS NEUTRONS BY 2120700100007 NATURAL URANIUM- 2120700100008 FACILITY (REAC ) GLEEP REACTOR AT AERE OPERATED 0.1 PERCENT 2120700100009 BELOW CRITICAL. 2120700100010 SAMPLE .THE KNOWN AMOUNT OF URANIUM ELEMENT (3.462E+04 KG) IN 2120700100011 THE GLEEP REACTOR CONSTITUTES THE SAMPLE. 2120700100012 METHOD .MEASUREMENT OF NEUTRON COUNT RATE IN BF-3 COUNTER IN 2120700100013 PILE AS A FUNCTION OF THE POSITION OF A CALIBRATED 2120700100014 RA-RE NEUTRON SOURCE ALONG THE PILE AXIS. 2120700100015 .REVISED SOURCE STRENGTH (9.09+-0.04)E+06, OLD VALUE 2120700100016 (9.66+-0.44)E+06 N/SEC. 2120700100017 DETECTOR (BF3) 3 INCH DIAMETER, 12 INCH LONG, BF-3 COUNTER 2120700100018 CONTAINING 6 TORR BF-3 AND 6 TORR ARGON. 2120700100019 PART-DET (N) REACTOR NEUTRONS. 2120700100020 CORRECTION .CORRECTION FOR ABSORPTION OF PILE NEUTRONS BY THE 2120700100021 SOURCE BY REPEATING MEASUREMENTS WITH A BRASS 2120700100022 CYLINDER OF THE SAME EFFECTIVE THERMAL ABSORPTION 2120700100023 CROSS-SECTION AS THE SOURCE. 2120700100024 .CORRECTION FOR NEUTRONS GENERATED BY (A,N) REACTIONS 2120700100025 FROM OXYGEN IN URANIUM OXIDE IN CORE, LESS THAN 2 2120700100026 PERCENT. 2120700100027 .ADDITIONAL CORRECTION TO REVISED VALUE FOR FAST 2120700100028 FISSION FACTOR FOR METAL REGION OF GLEEP, 2 PERCENT. 2120700100029 ERR-ANALYS (ERR-S) .STATISTICAL COUNTING ERROR ABOUT 1 PERCENT. 2120700100030 STATUS (NDD ) FROM NEUDADA. 2120700100031 HISTORY (19791207T) 2120700100032 (19800110E) 2120700100033 (20060809A) DATE and reference code corrected 2120700100034 ENDBIB 32 0 2120700100035 COMMON 1 3 2120700100036 ERR-S 2120700100037 PER-CENT 2120700100038 1.0 2120700100039 ENDCOMMON 3 0 2120700100040 ENDSUBENT 39 0 2120700199999 SUBENT 21207002 20060809 21782120700200001 BIB 2 4 2120700200002 REACTION (92-U-0(0,F),,NU,,FCT) 2120700200003 .DATA GIVEN IS SPONTANEOUS NEUTRON EMISSION IN 2120700200004 N/SEC/GM. 2120700200005 STATUS .REVISED DATA TAKEN FROM J,JNE/A,11,34,195911. 2120700200006 ENDBIB 4 0 2120700200007 NOCOMMON 0 0 2120700200008 DATA 1 1 2120700200009 DATA 2120700200010 ARB-UNITS 2120700200011 1.5200E-02 2120700200012 ENDDATA 3 0 2120700200013 ENDSUBENT 12 0 2120700299999 ENDENTRY 2 0 2120799999999