MCNP COMMAND GUIDE BLOCK 1: CELL CARD
ID M ρ surf
imp:x=z
eg. 10 0 20 1 -7.86
-10 10 -20
imp:p=1 imp:p=1
Cell 10 void space (i.e., vacuum) located inside surace 10 !it" imp or p"otons o 1
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Cell 20 •
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composed o material 1 deined in #loc$ % (&e) 'onl one material per cell !it" densit o -7.86 g*cm% located in t"e space o intersection o + o surace 10 and let o surace 20 !it" imp or p"otons o 1
cell num#er (no more t"an / digits) material num#er (deined later in #loc$ % as m1, m2, etc.) i =0, (no densit) no more t"an / digits 3 densit o t"e material (4) i atoms*#-1 cm-1 (-) i g*cm-% sur cell deinition !rt to #ounding suraces use union (5:) or intersection (5 ) o suraces to deine cell or planes, (-) i , and (4) i +, !rt to surace or enclosed suraces (eg. sp"ere, clinder), (-) 9 and (4) imp command or importance o t"e cell can also #e deined in #loc$ % ; tpe o particle p or p"otons e or electrons n or neutrons < value o importance usuall 1 or source cells closer to tall region "ave "ig" importance i <=0, $ill particles t"at enter t"e cell i <=1, trac$ particle pa rticle normall
BLOCK 2: SURACE CARD ! MACROBODIES ID M" CE
eg. 10 so %0.0 20 c*< / / 10 urace 10 p"ere centered at origin +=%0.0 cm • •
surace num#er n mnemonic or surace tpe(see ta#le) C> card entries (eg. radius, ;-coord) •
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can #e used or #ot" surace and macro#odies (see ta#le or reerence) C9? needs a #oundar around t"e pro#lem geometr #eond !"ic" t"e importance is
urace 20 eg. 100 so 1000 (edge o universe) clinder parallel to <-a;is ; @ -int = /,/A + = 10.0 cm BLOCK #: DA$A CARD ; material num#er (eg. 1, 20, etc.) BBB atomic num#er ( = 008, &e = 026) 555 mass num#er 000 or elementals 555 or isotopes (eg. 2%/ = 2%/) !*c ; BBB555.nn are usuall used or neutron transport .nn cross section compilation identiier (aterial peciication) atomic a#undance (eg. or D2, D is 2 and is 1) ; mass raction (eg. or D2, D is 1 8016 1 -0.111E0 and is -0.88810) 2 26000 1 mass raction = m<*mtot % 6000 1 i g*cm% is used (-) no densit component to allo! one material to appear at various densities • •
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BBB atomic num#er ( = 008, &e = 026) 555 mass num#er 000 or elementals 555 or isotopes (eg. 2%/ = 2%/) !*c are usuall used or neutron transport nn cross section evaluation identiier class o data or neutrons, ""C = continuous energ ta#le @ ""D = discrete reaction ta#le p"otoatomic = ""P (%1p = inco", co", p"otoelec, pair prod, etc.A %2p = e;t o 01p to "ig" energies 10 e to 1/*100 eA %#p = e;t o 02p #ut accounts momentum o e- or Compton pea$ #roadeningA 0Fp = ta#les rom >9&*-.8, 1$e to 100Ge, B=1 to 100, recommended data se p"otonuclear = ""U (>9&-6, 1% nuclides or electrons, ""E (&%1' = energ, rad • •
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BBB555.nn (Cross ection peciication)
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stp p!r, #remss, $-edge energies, auger e- prod energies, angular delA %&%#' = includes densit eect calc) neutron dosimetr = ""( neutron t"ermal (H,I) ta#les = ""$
speci t"e source and tpe o particles contains man varia#les and parameters (reer to ta#le %) >+G = energ in e ?5+ = tpe o particle source emits (n, n p, n p e =1A p, p e=2A e=%) ? = reerence pt or sampling (?=0 0 0) all deault is used, Just >& ; p or p"oton transport e or electron transport n or neutron (deault i mode is omitted) n p or neutron, neutron-induced p"oton p e or p"oton and electron transport n p e or neutron, neutron-induced p"oton and electron transport •
>& (ource peciication)
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? = ; <
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> ;
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?: C C C C
tpe o particle (i.e., 9 ? >) C importance o all cells in pro#lem i F cells in t"e pro#lem, F entries in ? command variance reduction tec"niKue 0 = termination o particleLs "istor sed or geometr splitting and +ussian roulette to "elp particles more easil to imp regions p or p"oton e or electron n or neutron n, p or neutron, neutron-induced p"oton •
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?:9 1 1 1 0
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&1: M &2: M &F: M
speci t"e tpe o source particle to #e trac$ed !"en mode is speciied, t"e ?5+ entr ma #e omitted in >&
&/: M &6: M &7: M &8: M (all peciication)
p,e or p"oton and electron M indicates surace or cell to #e evaluated &1 surace current (9 ? >)A N &2 surace lu; (9 ? >)A N*cm2 &F cell lu; (9 ? >)A N*cm2 &/ lu; at a point or ring (9 ?)A N*cm 2 &6 energ deposition(9 ? 9,?)A e*g &7 ission energ deposition in cell (9)A e*g &8 pulse "eig"t distri#ution (? > ?,>)A pulsesA total energ deposited # eac" p"sical particleA not recommended or neutrons •
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9? 9 (Distor Card) C> ?DM:? >C?& > 9CD ?99 9?
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?DM:? 100 0 0 0 0 Q100e, #rems, co" scat, no p"otonuc, oppler
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sed to speci !"at ou !ant to learn on C calculation Can #e increments o 10 (&1 = &11 = &21) &1, &2, &F, &/ are lagged !it" an asteris$ (O&1:9), tall o eac" event is multiplied # p"oton energ (results to tall o energ lu; or energ current) &6, &7 are lagged !it" an O, c"ange units rom e.g to Jer$s*g (1 Jer$ = 10E P) limits t"e ma;imum num#er o source particle "istories 9 limits "o! long C9? runs p"sics simpliication or p"oton and electron >C?& = energ in e a#ove !"ic" simple p"sics is to #e used > = 0*1 indicates i #remsstra"lung is included*ignored 9CD = 0*1 speci i co"erent scattering is included or ignored ?99 = -1*0*1 indicates i p"otonuclear interactions are used in analog manner* not used* used !* #ias 9? = 0*1 turns oppler #roadening
?DM:9 >5 >C9& 9+ 9
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C, Q
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/ #lan$s in 1st / columns, @
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>n >1 >2 >% >F (all >nerg Card)
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>2F 1 2 % F (up to F e) •
>n >1 ni >ma; Q n eKuispaced #ins #et!een >1 and >ma;
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on*o p"sics simpliication or neutron >5 = energ in e a#ove !"ic" neutron data is not placed in memor >C9& = energ in e !"erein neutrons #elo! >C9& is treated # analogue capture !"ile a#ove >C9& is treated # implicit capture 9+ = i 1, avgd a#ove resolved are usedA i 0, pro# ta#les descr interactions are sampled 9 speciies i v(>) includes prompt 4delaed n (-1) or i onl prompt n (0) or delaed n per ission are to #e used (R0) Comment cards !"ic" can #e place an!"ere in input ile C s"ould #e ollo!ed # a space and #e ound at columns 1-/ Q terminated data entr on a line / #lan$s indicate a continuation o data rom t"e last name card @ ending a line indicates data !ill continue on t"e ollo!ing card S"en ou !is" to su#divide total lu; or current tall num#er into energ groups ee lu; as a unction o energ +esults or tall 2F (tpe &F) are #inned in F energ groups >n card is a#sent, onl one #in over all energies >0 card = sets up a deault energ #in or 5 tallies
MCNP )ISUAL EDI$OR ORMA$
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itle Card Cell Card
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lan$ ine urace Cards lan$ ine ode ource (onl TC> and $src i t"e e;ist) aterials ransormations mportances t"er data (, ?S, >, &C, ?, C, 99, SS9, ?) ata not recogni
