neutron-UO2 c c -------------------------- Input Information ----------------------------- 80 c A 14.1-MeV neutron beam is incident on UO2 --> testing heavy ion creation c The UO2 layer thickness was varied and to test changes in the number of c heavy ion tracks created. There are a few additional tally regions I included c to double-check particle tracks and tallies. c The simulations were performed for UO2 in air for now. This simulation was c only used to determine %heavy ions that escaped the UO2 layer. c c -------------------------------------------------------------------------- 80 c ----------------------------- Cell Cards --------------------------------- 80 c -------------------------------------------------------------------------- 80 1 1 -10.97 -301 $Uranium Oxide (UO2) cylinder 2 0 -201 $Vacuum region for tallying particles entering in front 3 0 -202 $Vacuum region for tallying particles entering behind 4 0 (-203 204 600 -205) $Vacuum region for tallying particles entering cylindrical shell around all 5 0 -602 -600 601 $Vacuum region showing location of source in XMing 6 2 -0.001225 -101 #1 #2 #3 #4 #5 $Air inside everything, outside all other materials 7 0 101 $Particle Graveyard c -------------------------------------------------------------------------- 80 c ---------------------------- Surface Cards ------------------------------- 80 c -------------------------------------------------------------------------- 80 c ROOM AIR $Room air box: coordinates of corner followed by vectors 101 BOX -15 -25 -5 50 0 0 0 50 0 0 0 30 c Vacuum zones for tallies $These rcc & c/x zones are positioned at z = 11 cm, which is just a legacy position from a previous set of simulations. 201 rcc -1.1 0 11 0.05 0 0 2 $region for tallying electrons entering in front 202 rcc 24.5 0 11 0.1 0 0 10.5 $region for tallying particles entering behind 203 c/x 0 11 10.5 $region for tallying particles in surrounding cylindrical shell 204 c/x 0 11 10.4 205 px 24.45 $ also uses px from 600 and px above. small gap between this and back tally region c 301 rcc -0.74 0 11 0.500000 0 0 10 $UO2, r=10 cm, th= 0.5 cm here, but thickness is variable, Full cylider c Cylindrical region with a Surface Source near the UO2 layer side 600 px -1.2 $Slightly larger radius as source - volume just to show where source is located in XMing 601 px -1.5 602 c/x 0 11 2.01 c -------------------------------------------------------------------------- 80 c ----------------------------- Data Cards --------------------------------- 80 c -------------------------------------------------------------------------- 80 c Materials c Material 1: "Uranium Oxide-U235" (-10.97 g/cm^3) m1 8000.14p 0.6666 $ 92235.14p 0.3334 $Uranium-235 hstep=20 c c Material 2: "Air" (-0.001225 "g/cm^3") m2 6012. 0.00015 7014. 0.784431 8016. 0.210748 18040. 0.004671 c c c Mode mode n d t h s p a # $ e excluded c c Cell Importances (total cells in CELL CARD) imp:n 1 1 1 1 1 1 0 $7 per line c imp:e 1 1 1 1 1 1 0 $e- excluded imp:d 1 1 1 1 1 1 0 imp:t 1 1 1 1 1 1 0 imp:h 1 1 1 1 1 1 0 imp:s 1 1 1 1 1 1 0 imp:p 1 1 1 1 1 1 0 imp:a 1 1 1 1 1 1 0 imp:# 1 1 1 1 1 1 0 c c -------------------------------------------------------------------------- 80 c ---------------------------Phys Cards------------------------------------- 80 c -------------------------------------------------------------------------- 80 c format: phys:n emax emcnf iunr J J J coilf cutn J J J c i_int_model i_els_model c c PHYS:N 200 100 0 J J J 4 -1 J J J 0 0 $suggested trying coilf=1 c PHYS:E 100 0 0 0 0 1 1 1 1 0 0 J J 0.917 0.001 $default values right now PHYS:D 100 J J J 1 PHYS:t 100 J J J 1 phys:h 100 0 -1 j 0 j 1 j j j 0 0 0 0.917 j 0 0 phys:p 100 0 0 -1 0 j 1 PHYS:a 800 3J 1 5J 0 0 0 0.917 $Defaults except for Emax phys:# 200 J J J 0 J J J 1 j j j 0 0 c c -------------------------------------------------------------------------- 80 c ---------------------------- Sources ------------------------------------- 80 c -------------------------------------------------------------------------- 80 c Source Definition c Distribution of Energy neutrons: sdef SUR=600 POS=-1.2 0 11 VEC 1 0 0 RAD=d1 DIR=1 par=n erg=14.1 si1 H 0 2 $Source radius sp1 -21 1 $power law: proportional to radius for even areal dist. c sp2 -3 1.025 2.926 $Option for Watt Distribution c nps 1e8 LCA 8j 1 $ use CEM03.03 ACT Fission=all c c -------------------------------------------------------------------------- 80 c ---------------------------- Tallies ------------------------------------- 80 c -------------------------------------------------------------------------- 80 c ----neutrons fc114 tally "F114n-UO2" f114:n ( 1 ) E114 0.1 198i 20 c Energy Bins for incoming/outgoing neutrons in the UO2 c c ----photons fc214 tally "F214p-UO2" f214:p ( 1 ) E214 0.1 198i 20 c Energy Bins for incoming/outgoing photons in the UO2 c c ----Heavy Ions fc334 tally "F334#-UO2" f334:# ( 1 ) $attempting one Z=10-50 E334 0.1 198i 20 c FT334 RES 10 50 $excluded this time c Energy Bins for incoming/outgoing heavy ions in UO2 c fc344 tally "F344#-behind" f344:# ( 3 ) $attempting one Z=10-50 E344 0.1 198i 20 c FT344 RES 10 50 $excluded this time c Energy Bins for incoming/outgoing heavy ions behind c fc354 tally "F354#-around" f354:# ( 4 ) $attempting one Z=10-50 E354 0.1 198i 20 c FT354 RES 10 50 $excluded this time c Energy Bins for incoming/outgoing heavy ions in around c c c --------------------------- CUT Cards ------------------------------------ 80 c Below: need to specifically define lower energy cutoffs instead of defaults cut:n j 0 c cut:e j 1e-5 cut:d j 1e-3 cut:t j 1e-3 cut:h j 1e-3 $ These are the lower limits of MCNP cut:s j 1e-3 $ This sets the lower energy cutoff to 1keV. cut:p j 1e-3 cut:# j 0 c c -------------------------- Trying DBCN Card------------------------------- 80 DBCN 27J 200000 $Debug card. x28 deals with bank size. c max value of DBCN is 8-byte integer, so up to >18E18? c -------------------------- Trying DBCN Card------------------------------- 80 rand gen=2 seed=1 stride=500000 print -85 -86 -87 -98 -110 c c --------------------------- End Data Cards ------------------------------- 80 c End MCNP Input