ENTRY 22054 19890207 00002205400000001 SUBENT 22054001 19890207 00002205400100001 BIB 18 41 2205400100002 REFERENCE (J,RCA,18,(4),202,7212) 2205400100003 TITLE -RELATIVE YIELDS OF SOME GAMMA-RAY EMITTING NUCLIDES 2205400100004 FROM THERMAL NEUTRON FISSION OF U-235. 2205400100005 AUTHOR (K.DEBERTIN) 2205400100006 INSTITUTE (2GERPTB) 2205400100007 FACILITY (REAC ) FORSCHUNGS- UND MESSREAKTOR FMRB, BRAUN- 2205400100008 SCHWEIG, AND FORSCHUNGSREAKTOR FR2, KARLSRUHE. 2205400100009 INC-SOURCE (REAC ) THERMAL REACTOR. 2205400100010 INC-SPECT .THERMAL REACTOR SPECTRUM. FLUX DENSITIES WERE 2205400100011 BETWEEN 0.02E+12 AND 70.0E+12 NEUTRONS/CM2 SEC. 2205400100012 METHOD .DIRECT GAMMA-RAY SPECTROMETRIC METHODS. 2205400100013 SIMULTANEOUS MEASUREMENT OF ACTIVITIES FROM SEVERAL 2205400100014 FISSION PRODUCTS. CALIBRATION WITH STANDARD SOURCES 2205400100015 OF THE SAME NUCLIDES. 2205400100016 DETECTOR (GELI ) GELI SPECTROMETER, WITH 2.8 KEV RESOLUTION 2205400100017 AT 1333 KEV. DISTANCE BETWEEN SAMPLE AND DETECTOR 2205400100018 WAS 10 TO 90 CM, DEPENDING ON ACTIVITY. 2205400100019 MONITOR (92-U-235(N,F)58-CE-144,CUM,FY,,SPA) 2205400100020 DECAY-MON (58-CE-144,284.D,DG,134.) 2205400100021 SAMPLE .PLATE SECTIONS OF MTR-FUEL ELEMENTS. MEASURMENTS 2205400100022 WERE PERFORMED ON AN INTERMEDIATE LAYER WITH THE 2205400100023 DIMENSIONS 40 * 20 * 0.6 MM, CONTAINING A URANIUM 2205400100024 ALUMINIUM ALLOY WITH ABOUT 300 MILLI-G URANIUM, 2205400100025 ENRICHED TO 90 PER CENT U-235. IRRADIATION TIMES 2205400100026 WERE BETWEEN 40 SEC AND 109 DAYS. 2205400100027 CORRECTION .CORRECTIONS WERE APPLIED FOR SELF ABSORPTION AND 2205400100028 MEASURING GEOMETRY. 2205400100029 .A SMALL CORRECTION DUE TO FAST FISSION YIELDS 2205400100030 WERE APPLIED FOR RU-106. 2205400100031 ERR-ANALYS (DATA-ERR) THE QUOTED UNCERTAINTIES CORRESPOND TO 2205400100032 A CONFIDENCE LEVEL OF 68 PER CENT. 2205400100033 ANALYSIS .THE GIVEN VALUES ARE AVERAGES OF SEVERAL MEASURE- 2205400100034 MENTS. 2205400100035 COMMENT .MONITOR DATA TAKEN FROM E.A.C. CROUCH, VALUES 2205400100036 RECOMMENDED BY THE CHEMICAL NUCLEAR DATA COMMITTEE, 2205400100037 U.K.A.E.A., TO BE PUBLISHED. 2205400100038 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2205400100039 HISTORY (871109C) N.O. 2205400100040 (871211E) 2205400100041 (880808U) IF. 2205400100042 (880810E) 2205400100043 ENDBIB 41 0 2205400100044 COMMON 3 3 2205400100045 EN-DUMMY MONIT MONIT-ERR 2205400100046 EV PC/FIS PC/FIS 2205400100047 2.5300E-02 5.3500E+00 8.0000E-02 2205400100048 ENDCOMMON 3 0 2205400100049 ENDSUBENT 48 0 2205400199999 SUBENT 22054002 19881222 00002205400200001 BIB 4 13 2205400200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 2205400200003 DECAY-DATA (40-ZR-95,64.1D,DG,724.,,DG,757.) 2205400200004 (44-RU-103,39.4D,DG,497.,,DG,610.) 2205400200005 (44-RU-106,369.D,DG,512.,,DG,622.) 2205400200006 (53-I-131,8.02D,DG,364.) 2205400200007 (55-CS-137,10921.D,DG,662.) 2205400200008 (56-BA-140,12.74D,DG,537.) 2205400200009 (57-LA-140,1.67D,DG,329.,,DG,487.,,DG,816.,,DG,1596.) 2205400200010 (58-CE-141,32.5D,DG,145.) 2205400200011 (59-PR-144-G,17.3MIN,DG,696.,,DG,2186.) 2205400200012 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2205400200013 HISTORY (871109C) N.O. 2205400200014 (871211E) 2205400200015 ENDBIB 13 0 2205400200016 NOCOMMON 0 0 2205400200017 DATA 4 6 2205400200018 ELEMENT MASS DATA DATA-ERR 2205400200019 NO-DIM NO-DIM PC/FIS PC/FIS 2205400200020 4.0000E+01 9.5000E+01 6.5200E+00 7.0000E-02 2205400200021 4.4000E+01 1.0300E+02 3.0600E+00 4.0000E-02 2205400200022 4.4000E+01 1.0600E+02 3.9900E-01 6.0000E-03 2205400200023 5.3000E+01 1.3100E+02 2.9100E+00 3.0000E-02 2205400200024 5.6000E+01 1.4000E+02 6.3000E+00 9.0000E-02 2205400200025 5.8000E+01 1.4100E+02 5.7500E+00 6.0000E-02 2205400200026 ENDDATA 8 0 2205400200027 ENDSUBENT 26 0 2205400299999 ENDENTRY 2 0 2205499999999