ENTRY 20738 19840201 00002073800000001 SUBENT 20738001 19840201 00002073800100001 BIB 15 36 2073800100002 INSTITUTE (2BLGGHT) 2073800100003 REFERENCE (J,RCA,10,11,68) 2073800100004 AUTHOR (M.DESCHUYTER,D.L.MASSART,A.SPEECKE,J.HOSTE) 2073800100005 TITLE -THE MEAN REACTOR CROSS SECTION FOR THE (N,P) 2073800100006 REACTION ON CE-140.- 2073800100007 INC-SOURCE (REAC ) BR-1 AND BR-2 REACTOR (MOL,BELGIUM) 2073800100008 INC-SPECT .FAST NEUTRON FLUX OF BR-2 REACTOR. 2073800100009 SAMPLE .SOLUTION OF CE(NH4)2(NO3)6 IN WATER. BY ACTIVATION 2073800100010 ANALYSIS THIS PRODUCT WAS FOUND TO CONTAIN 12 P.P.M. 2073800100011 LA-139. THIS AMOUNT OF LA-139 IS TOO MUCH TO ALLOW 2073800100012 THE DETERMINATION OF THE CROSS SECTION OF THE (N,P)- 2073800100013 REACTION BECAUSE BY (N,G)-REACTION IT YIELDS THE 2073800100014 SAME ENDPRODUCT. THE SEPARATION WAS MADE BY CATION 2073800100015 EXCHANGE WITH A-ISOHYDROXYDROBUTYRATE . 2073800100016 METHOD (ACTIV) ACTIVATION AND CHEMICAL SEPARATION. 2073800100017 DETECTOR (NAICR) NAI(TL)-DETECTOR COUPLED TO A 400 CHANNEL 2073800100018 ANALYSER. 2073800100019 ANALYSIS .IRRADIATIONS WITH AND WITHOUT CD-SHIELDING IN ORDER 2073800100020 TO DETERMINE THE LA CONTENT OF THE CE-MATRIX. 2073800100021 MONITOR (28-NI-58(N,2N)28-NI-57,,SIG,,FIS) 2073800100022 EFFECTIVE THRESHOLD = 12.0 MEV, 2073800100023 AVERAGE FISSION SPECTRUM CROSS SECTION = 0.004 MBARNS 2073800100024 (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 2073800100025 EFFECTIVE THRESHOLD = 4.1 MEV, 2073800100026 AVERAGE FISSION SPECTRUM CROSS SECTION = 100 MBARNS 2073800100027 (13-AL-27(N,A)11-NA-24,,SIG,,FIS) 2073800100028 EFFECTIVE THRESHOLD = 8.1 MEV, 2073800100029 AVERAGE FISSION SPECTRUM CROSS SECTION = 0.56 MBARNS 2073800100030 .FOR THE THERMAL FLUX CO-MONITORS (1 PER CENT CO-AL 2073800100031 ALLOY) HAVE BEEN USED. 2073800100032 STATUS .TAKEN FROM RADIOCHIMICA ACTA 10(1968)11. 2073800100033 HISTORY (770405C) 2073800100034 (780307E) 2073800100035 CORRECTION .THE INTERFERENCE OF CE-138(N,G)-REACTION IN THE 2073800100036 DETERMINATION OF LA-140 IS NEGLIGIBLE. 2073800100037 ERR-ANALYS .NO DETAILS GIVEN. 2073800100038 ENDBIB 36 0 2073800100039 NOCOMMON 0 0 2073800100040 ENDSUBENT 39 0 2073800199999 SUBENT 20738002 19840201 00002073800200001 BIB 3 13 2073800200002 REACTION (58-CE-140(N,P)57-LA-140,,SIG,,FIS) 2073800200003 FLAG (1.) EXPERIMENT 1,REFERENCE REACTION NI-58(N,P). 2073800200004 (2.) EXPERIMENT 2,REFERENCE REACTION NI-58(N,P). 2073800200005 (3.) EXPERIMENT 3,REFERENCE REACTION NI-58(N,P). 2073800200006 (4.) EXPERIMENT 1,REFERENCE REACTION AL-27(N,A). 2073800200007 (5.) EXPERIMENT 2,REFERENCE REACTION AL-27(N,A). 2073800200008 (6.) EXPERIMENT 3,REFERENCE REACTION AL-27(N,A). 2073800200009 (7.) EXPERIMENT 1,REFERENCE REACTION NI-58(N,2N). 2073800200010 (8.) EXPERIMENT 2,REFERENCE REACTION NI-58(N,2N). 2073800200011 (9.) EXPERIMENT 3,REFERENCE REACTION NI-58(N,2N). 2073800200012 (10.) AVERAGE VALUE WITH REFERENCE REACTION NI-58(N,2N)2073800200013 HISTORY (770405C) 2073800200014 (780307E) 2073800200015 ENDBIB 13 0 2073800200016 COMMON 1 3 2073800200017 EN-DUMMY 2073800200018 MEV 2073800200019 1.5000E+00 2073800200020 ENDCOMMON 3 0 2073800200021 DATA 3 10 2073800200022 DATA DATA-ERR FLAG 2073800200023 B B NO-DIM 2073800200024 4.9000E+00 3.0000E+00 2073800200025 4.3600E+00 1.0000E+00 2073800200026 4.1900E+00 6.0000E+00 2073800200027 3.8000E+00 9.0000E+00 2073800200028 3.7900E+00 4.0000E+00 2073800200029 3.4700E+00 7.0000E+00 2073800200030 3.4400E+00 5.0000E+00 2073800200031 3.4000E+00 8.0000E-01 1.0000E+01 2073800200032 3.1000E+00 8.0000E+00 2073800200033 2.7900E+00 2.0000E+00 2073800200034 ENDDATA 12 0 2073800200035 ENDSUBENT 34 0 2073800299999 ENDENTRY 2 0 2073899999999