* EX.1)ZED-2 TASK 1 COOL=D2O METHOD=DSN ************************************** * PREUDE DATA CELL 7 * CLUSTER (D5B = CLUSTER) SEQUENCE 1 * DSN NGROUP 69 3 * MAIN TRANSPORT SOLUTION/REACTION EDIT # OF GROUPS NMESH 35 * #MESH POINTS IN MAIN TRANSPORT ROUTINE NREGION 9 4 * #ANNULI/#ANNULI CONTAINING RODS NMATERIAL 11 0 * #MATS/#MATS UNDERGOING BURNUP * NRODS 37 -6 100 11 4 3 1 NREACT 5 * #NUCLIDE REACTION RATE EDITS PREOUT * (D5B = ENDP) * MAIN DATA INITIATE * GEOMETRY DATA ANNULUS 1 0.831230 1 ANNULUS 2 2.199230 1 ANNULUS 3 3.623250 1 ANNULUS 4 5.056180 1 ANNULUS 5 5.1950 1 ANNULUS 6 5.51180 3 ANNULUS 7 6.35000 4 ANNULUS 8 6.66750 5 ANNULUS 9 16.121710 2 ARRAY 1 1 1 0 0 * RING OF R=0 OF 1 ROD (ANG 0) ARRAY 2 1 6 1.488440 0 * RING OF R=1.48844 OF 6 RODS (ANG 0) ARRAY 3 1 12 2.875280 0.261799 * RING OF R=2.87528 OF 12 RODS (ANG 0.2617) ARRAY 4 1 18 4.33070 0 * RING OF R=4.33070 OF 18 RODS (ANG 0) RODSUB 1 1 0.58674 6 RODSUB 1 2 0.61240 10 RODSUB 1 3 0.65525 11 RODSUB 2 1 0.603671 7 RODSUB 2 2 0.61240 10 RODSUB 2 3 0.65525 11 RODSUB 3 1 0.603671 8 RODSUB 3 2 0.61240 10 RODSUB 3 3 0.65525 11 RODSUB 4 1 0.603671 9 RODSUB 4 2 0.61240 10 RODSUB 4 3 0.65525 11 CRAIG * COMPOSITION DATA * m.1= d2o coolant MATERIAL 1 1.104676 294.8000 3 3002 20.062 $ 3001 0.029 $ 6016 79.909 * m.2= external moderator - heavy water - 3002: deuterium * 3001: hydrogen * 6016: oxygen-16 MATERIAL 2 1.104676 294.8000 4 3002 20.062 $ 3001 0.029 $ 6016 79.909 * m.3= pressure tube - al - 1010: boron-10 * 27: aluminium-27 MATERIAL 3 2.700000 294.8000 4 1010 5.7000E-04 $ 27 99.99943 * m.4= gap between press.and cal.tubes - o - 6016: oxygen-16 MATERIAL 4 1.40E-03 294.8000 4 6016 100.0000 * m.5= calandria tube - al - 1010: boron-10 * 27: aluminium-27 MATERIAL 5 2.700000 294.8000 4 1010 3.0000E-04 $ 27 99.99970 * m.6= fuel rods type 1 - natural uo2 - 8238.0: uranium-238 * 2235.0: uranium-235 * 6016 : oxygen-16 MATERIAL 6 10.550000 294.8000 1 8238.0 87.5227 $ 2235.0 0.6271 $ 6016 11.8502 * m.7= fuel rods type 2 - natural uo2 - 8238.0: uranium-238 * 2235.0: uranium-235 * 6016 : oxygen-16 MATERIAL 7 10.550000 294.8000 1 8238.0 87.5227 $ 2235.0 0.6271 $ 6016 11.8502 * m.8= fuel rods type 3 - natural uo2 - 8238.0: uranium-238 * 2235.0: uranium-235 * 6016 : oxygen-16 MATERIAL 8 10.550000 294.8000 1 8238.0 87.5227 $ 2235.0 0.6271 $ 6016 11.8502 * m.9= fuel rods type 4 - natural uo2 - 8238.0: uranium-238 * 2235.0: uranium-235 * 6016 : oxygen-16 MATERIAL 9 10.550000 294.8000 1 8238.0 87.5227 $ 2235.0 0.6271 $ 6016 11.8502 * m.10= gap between fuel and clad - o - 6016: oxygen-16 MATERIAL 10 1.40E-03 294.8000 2 6016 100.0000 * m.11= clad - zr - 91: zyrconium-91 MATERIAL 11 6.550000 294.8000 2 91 100.0000 * 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 5 5 1 2 2 2 10 * #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 1.550E-04 1.150E-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 1.9146E-04 6.6274E-02 3.3240E-02 0.0 DNB 2 1.9146E-04 6.6274E-02 3.3240E-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 DNB 9 0.0 0.0 0.0 0.0 DNB 10 0.0 0.0 0.0 0.0 DNB 11 0.0 0.0 0.0 0.0 DIFFUSION 2 * TRANSPORT * REACTION RATE EDIT * 176 : Lu-176 * 55 : Mn-55 * 3063 : Cu-63 * 2235.0: U-235 * 8238.0: U-238 REACTION 176 294.8 $ 55 294.8 $ 3063 294.8 $ 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