* EX.1)ZED-2 TASK 2 PITCH=24 cm METHOD=DSN ********************************** * PREUDE DATA CELL 7 * CLUSTER (D5B = CLUSTER) SEQUENCE 1 * DSN NGROUP 69 3 * MAIN TRANSPORT SOLUTION/REACTION EDIT # OF GROUPS NMESH 28 * #MESH POINTS IN MAIN TRANSPORT ROUTINE NREGION 8 3 * #ANNULI/#ANNULI CONTAINING RODS NMATERIAL 8 0 * #MATS/#MATS UNDERGOING BURNUP * NRODS 28 -8 100 11 3 3 1 NREACT 2 * #NUCLIDE REACTION RATE EDITS PREOUT * (D5B = ENDP) * MAIN DATA INITIATE * GEOMETRY DATA ANNULUS 1 1.94604 1 * coolant d2o ANNULUS 2 3.33146 1 * " ANNULUS 3 5.07166 1 * " ANNULUS 4 5.095 1 * " ANNULUS 5 5.390 3 * pt Al65s ANNULUS 6 6.230 4 * gap gas ANNULUS 7 6.370 5 * ct Al50s ANNULUS 8 12.6009 2 * moderator d2o ARRAY 1 1 4 1.163 .785398 * RING OF R=1.163 OF 4 RODS ARRAY 2 1 8 2.652 .392699 * RING OF R=2.652 OF 8 RODS ARRAY 3 1 16 4.206 .196349 * RING OF R=4.206 OF 16 RODS RODSUB 1 1 0.710 6 RODSUB 1 2 0.715 7 RODSUB 1 3 0.76 8 RODSUB 2 1 0.710 6 RODSUB 2 2 0.715 7 RODSUB 2 3 0.76 8 RODSUB 3 1 0.710 6 RODSUB 3 2 0.715 7 RODSUB 3 3 0.76 8 CRAIG * COMPOSITION DATA * m.1= coolant - heavy water - 3002/2002: deuterium in d2o * 3001/6001: hydrogen in h2o * 6016/ 16: oxygen MATERIAL 1 1.1046 296.50 3 3002 20.074 $ 3001 0.022 $ 6016 79.904 * m.2= external moderator - heavy water - 3002: deuterium in d2o * 3001: hydrogen in h2o * 6016: oxygen-16 MATERIAL 2 1.1046 296.50 4 3002 20.074 $ 3001 0.022 $ 6016 79.904 * m.3= pressure tube - al65S MATERIAL 3 2.70 296.50 4 24 1.00 $ 27 97.08 $ 29 0.60 $ 52 0.20 $ 55 0.15 $ 2056 0.70 $ 3063 0.27 * m.4= gas gap - o - 6016: oxygen-16 MATERIAL 4 1.40E-03 296.50 4 6016 100.0000 * m.5= calandria tube - al50S MATERIAL 5 2.70 296.50 4 24 0.90 $ 27 97.25 $ 29 1.00 $ 52 0.05 $ 55 0.10 $ 2056 0.60 $ 3063 0.10 * m.6= fuel rods - natural uo2 - 8238.0: uranium-238 * 2235.0: uranium-235 * 6016 : oxygen-16 MATERIAL 6 10.02770 296.50 1 8238.0 87.5183 $ 2235.0 0.6267 $ 6016 11.8502 * m.7= gas gap - o - 6016: oxygen-16 MATERIAL 7 1.40E-03 296.50 2 6016 100.0000 * m.8= clad - zry-2 MATERIAL 8 7.15368 296.50 2 27 5.8059 $ 91 94.1941 * CROSS SECTIONS AND FLUX SOLUTION FEWGROUPS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 $ 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 $ 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 $ 61 62 63 64 65 66 67 68 69 MESH 4 4 4 1 2 2 2 9 * #MESH INTERVS.OF EQUAL VOL.IN EACH OF THE ANNULI S 12 * Sn ORDER (SEQUENCE 1) REGULAR 1 * PRINTOUT CONTROL SUPPRESS 0 0 1 1 1 1 1 1 1 1 1 1 0 0 0 1 * END OF DATA BEGINC * EDIT DATA * LEAKAGE CALCULATIONS BUCKLING 1.4020E-04 1.4020E-04 * RADIAL/AXIAL BUCKLINGS NOBUCKLING * NO SEARCH FOR CRITICAL BUCKLING THERMAL 25 * #THERMAL GROUPS IN THE FEWGROUP SCHEME FOR TWO GROUP LEAKAGE EDIT BEEONE 1 DNB 1 1.4523E-04 6.6309E-02 3.3236E-02 0.0 DNB 2 1.4523E-04 6.6309E-02 3.3236E-02 0.0 DNB 3 0.0 0.0 0.0 0.0 DNB 4 0.0 0.0 0.0 0.0 DNB 5 0.0 0.0 0.0 0.0 DNB 6 0.0 0.0 0.0 0.0 DNB 7 0.0 0.0 0.0 0.0 DNB 8 0.0 0.0 0.0 0.0 DIFFUSION 2 * TRANSPORT * REACTION RATE EDIT * 2235.0: U-235 * 8238.0: U-238 REACTION 2235.0 294.8 $ 8238.0 294.8 PARTITION 5 45 69 * COMBINATION OF LIBRARY GROUPS REQUIRED IN EDIT OF REACTIONS LEAKAGE 5 *LEAKAGE SPECTRUM WITH INPUT BUCKLING FOR K-EFF NUCLIDE REACTION EDIT PRINTC 0 0 0 1 * REACTION RATES BY MESH/BY MAT/REACTIONS BY MAT/NO K-INF EDIT * END OF DATA BEGINC *END