ENTRY 21866 20060807 21782186600000001 SUBENT 21866001 20060807 21782186600100001 BIB 15 49 2186600100002 INSTITUTE (2JPNETL) ELECTROTECHNICAL LABORATORY, RADIATION 2186600100003 METROLOGY SECTION. 2186600100004 REFERENCE (P,NEANDC(J)-83/U,5,198209) 2186600100005 AUTHOR (K.KUDO,T.KINOSHITA,Y.KAWADA,T.MICHIKAWA) 2186600100006 TITLE -THERMAL CROSS SECTION RATIO SIGMA(H)/SIGMA(MN).- 2186600100007 INC-SOURCE (CF252) 5.4 MILLI-CURIE AT THE CENTRE OF AN 2186600100008 ALUMINIUM SPHERICAL SHELL OF 9.1 CM DIAMETER 2186600100009 WHICH WAS PLACED IN ITS TURN AT THE CENTRE OF 2186600100010 THE MAGNESIUM BATH VESSEL. THE NEUTRONS ARE 2186600100011 THERMALISED BY THE BATH. THE SPECTRUM IS 2186600100012 EVALUATED BY THE GOLD-ACTIVATION METHOD, USING 2186600100013 ALSO CADMIUM FOILS. 2186600100014 INC-SPECT .THERMAL MAXWELLIAN SPECTRUM. 2186600100015 SAMPLE .THE BATH ITSELF. 2186600100016 METHOD (MANGB) MANGANESE BATH INSIDE A SPHERICAL SUS316 2186600100017 VESSEL, 1.5 MM THICK AND WITH AN INTERNAL DIAMETER 2186600100018 OF 98.4 CM. 2186600100019 .ACTIVATION. THE CONCENTRATION OF MN-S-O(4) INSIDE 2186600100020 THE BATH IS CHANGED. THE CROSS SECTION IS OBTAINED 2186600100021 FROM A STRAIGHT LINE EQUATION RELATING THE ACTIVATION 2186600100022 OF THE BATH TO THE CONCENTRATION. THE ACTIVATION 2186600100023 IS MEASURED BY PUMPING THE SOLUTION FROM THE 2186600100024 BATH AND COUNTING IT IN 2186600100025 DETECTOR (NAICR) 2 NA-I CRYSTAL DETECTORS, RESP. 2.5 CM DIAM * 2186600100026 2.5 CM LONG AND 5.1 CM DIAM * 5.1 CM LONG, BOTH 2186600100027 COUPLED TO TEMPERATURE COMPENSATED PM BASES. THE 2186600100028 EFFICIENCY OF THE BATH WAS DETERMINED AS FOLLOWS - 2186600100029 MN-055 WAS ACTIVATED IN A REACTOR. A PART OF SUCH A 2186600100030 SAMPLE WAS INTRODUCED INTO THE BATH AND COUNTED, 2186600100031 ANOTHER PART WAS COUNTED IN A 2186600100032 (D4PI ) 4*PI B-G COINCIDENCE MEASUREMENT. 2186600100033 (LONGC) A STANDARD LONG COUNTER OF THE HANSON AND 2186600100034 MCKIBBEN TYPE WAS USED TO EVALUATE THE NEUTRON 2186600100035 ESCAPE FROM THE BATH. AND A 2186600100036 (BF3 ) BF3 COUNTER WAS USED TO MEASURE THE THERMAL 2186600100037 NEUTRONS AT THE SURFACE OF THE BATH. 2186600100038 PART-DET (DG) DECAY GAMMAS. ALL GAMMAS WITH AN ENERGY 2186600100039 GREATER THAN 20 KEV WERE INTEGRATED. 2186600100040 COMMENT .METHOD ALSO DESCRIBED IN AEJ,23,1(1980)62. 2186600100041 CORRECTION .NEUTRON ABSORPTION IN SOURCE AND SOURCE MOUNTING. 2186600100042 .(N,A) AND (N,P) REACTIONS. 2186600100043 .NON 1/V ACTIVATION. 2186600100044 ERR-ANALYS (ERR-T) NO DETAILS GIVEN. 2186600100045 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2186600100046 HISTORY (19830804C) G.C. 2186600100047 (19831004E) 2186600100048 (19840106U) A.P.T. JAPAN CODE CHANGED TO JPN 2186600100049 (19840106E) 2186600100050 (20060807A) DATE AND INSTITUTE CODES ARE corrected 2186600100051 ENDBIB 49 0 2186600100052 COMMON 1 3 2186600100053 EN-DUMMY 2186600100054 EV 2186600100055 2.5300E-02 2186600100056 ENDCOMMON 3 0 2186600100057 ENDSUBENT 56 0 2186600199999 SUBENT 21866002 20060807 21782186600200001 BIB 3 5 2186600200002 REACTION ((1-H-1(N,G)1-H-2,,SIG,,MXW)/ 2186600200003 (25-MN-55(N,G)25-MN-56,,SIG,,MXW)) 2186600200004 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2186600200005 HISTORY (19830804C) G.C. 2186600200006 (19831004E) 2186600200007 ENDBIB 5 0 2186600200008 NOCOMMON 0 0 2186600200009 DATA 2 1 2186600200010 DATA ERR-T 2186600200011 NO-DIM NO-DIM 2186600200012 2.5000E-02 8.0000E-05 2186600200013 ENDDATA 3 0 2186600200014 ENDSUBENT 13 0 2186600299999 ENDENTRY 2 0 2186699999999