Core cards
betaeff : Effective fractions of delayed neutrons
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Beta-effective in 6 time groups
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
betaeff 0.000285 0.0015975 0.00141 0.0030525 0.00096 0.000195 # a comment can also be put here
Number of values (i.e. number of the time groups) should be the same as in card dnplmb.
coregeom : Core geometry
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Core geometry
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
##### geometry pitch(m) botBC topBC
coregeom hex06 0.18018 0 0
geometry: flag of core geometry:square: square geometry;hex01: hexagonal geometry with 1 node per hexagon;hex06: hexagonal geometry with 6 node per hexagon;hex24: hexagonal geometry with 24 node per hexagon.
pitch: distance between centers of nodes in plane (m);botBC: flag of bottom boundary conditions:0: vacuum boundary condition-1: reflective boundary condition
topBC: flag of top boundary conditions:0: vacuum boundary condition-1: reflective boundary condition
coremap : Core map
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Core map
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
coremap 0 0 0 0 0 0 0 0 0 #1
coremap 0 0 SHI SHI SHI SHI 0 0 0 #2
coremap 0 0 SHI BLA BLA BLA SHI 0 0 #3
coremap 0 SHI BLA FIS FIS BLA SHI 0 0 #4
coremap 0 SHI BLA FIS FIS FIS BLA SHI 0 #5
coremap 0 SHI BLA FIS FIS BLA SHI 0 0 #6
coremap 0 0 SHI BLA BLA BLA SHI 0 0 #7
coremap 0 0 SHI SHI SHI SHI 0 0 0 #8
coremap 0 0 0 0 0 0 0 0 0 #9
The coremap card defined one row of assemblies in the core and consists of either boundary condition flag (0 : vaccuum; 1 : reflective) or of a stack id (should appear in the stack card).
dnplmb : Delayed neutron precursor decay time constants
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Delayed neutron precursor decay time constants in 6 time groups (1/s)
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
dnplmb 0.0127 0.0317 0.115 0.311 1.4 3.87
Number of values (i.e. number of the time groups) should be the same as in card betaeff.
mix : Homogeneous mix of isotopes
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Mix: fuel in inner zone
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
##### id isoid numdens sigtemp
mix INNER U235j311 3.58838E-05 TEMP
mix INNER U238j311 7.05072E-03 TEMP
mix INNER Pu238j311 6.31883E-06 TEMP
mix INNER Pu239j311 8.71553E-04 TEMP
mix INNER Pu240j311 2.59858E-04 TEMP
mix INNER Pu241j311 6.98635E-05 TEMP
mix INNER Pu242j311 2.42475E-05 TEMP
mix INNER Am241j311 1.70991E-05 TEMP
mix INNER O16j311 1.65043E-02 TEMP
mix INNER C0j311 4.75629E-05 TEMP
mix INNER Si28j311 2.25772E-04 TEMP
mix INNER Si29j311 1.10737E-05 TEMP
mix INNER Si30j311 7.06525E-06 TEMP
mix INNER P31j311 1.10562E-05 TEMP
mix INNER Ti46j311 8.19752E-06 TEMP
mix INNER Ti47j311 7.23535E-06 TEMP
mix INNER Ti48j311 7.02030E-05 TEMP
mix INNER Ti49j311 5.04663E-06 TEMP
mix INNER Ti50j311 4.73566E-06 TEMP
mix INNER Cr50j311 1.58887E-04 TEMP
mix INNER Cr52j311 2.94632E-03 TEMP
mix INNER Cr53j311 3.27778E-04 TEMP
mix INNER Cr54j311 8.00808E-05 TEMP
mix INNER Mn55j311 3.53226E-04 TEMP
mix INNER Fe54j311 8.00560E-04 TEMP
mix INNER Fe56j311 1.21188E-02 TEMP
mix INNER Fe57j311 2.74958E-04 TEMP
mix INNER Fe58j311 3.59615E-05 TEMP
mix INNER Ni58j311 1.87786E-03 TEMP
mix INNER Ni60j311 6.99261E-04 TEMP
mix INNER Ni61j311 2.98974E-05 TEMP
mix INNER Ni62j311 9.37938E-05 TEMP
mix INNER Ni64j311 2.31362E-05 TEMP
mix INNER Mo92j311 4.51168E-05 TEMP
mix INNER Mo94j311 2.78070E-05 TEMP
mix INNER Mo95j311 4.76300E-05 TEMP
mix INNER Mo96j311 4.96037E-05 TEMP
mix INNER Mo97j311 2.82709E-05 TEMP
mix INNER Mo98j311 7.10924E-05 TEMP
mix INNER Mo100j311 2.80498E-05 TEMP
mix INNER Na23j311 7.63797E-03 TEMP
mix INNER He4j311 6.11441E-07 TEMP
id: user-defined id of the mix;isoid: id of the isotope; the GENDF file with this name should exist in nuclear data directorynddir;numdens: number density of the isotopeisoidin the mixid(barn-1 cm-1);sigtemp: signal defining the temperature in K of the isotopeisoidin the mixid.
nddir : Nuclear data directory
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Nuclear data directory
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
nddir DATA25
nddir : path to directory containing multigroup cross-section files in GENDF format.
power0 : Initial reactor power
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Initial reactor power
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
power0 2990.e6
power0: initial reactor power (W).
stack : Vertical stack of homogeneous mixes
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Stack of mixes: fissile subassembly of inner zone
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
##### id mixid pipeid pipenode
stack FIN PLUG1 UP01 1
stack FIN GASPLE1 UP02 1
stack FIN GASPLE1 UP02 2
stack FIN GASPLE1 UP02 3
stack FIN GASPLE1 UP02 4
stack FIN GASPLE1 UP02 5
stack FIN GASPLE1 UP02 6
stack FIN GASPLE1 UP02 7
stack FIN GASPLE1 UP02 8
stack FIN GASPLE1 UP03 1
stack FIN GASPLE1 UP04 1
stack FIN SUPPOR1 UP05 1
stack FIN AXBLA UP06 1
stack FIN AXBLA UP06 2
stack FIN AXBLA UP06 3
stack FIN AXBLA UP06 4
stack FIN AXBLA UP06 5
stack FIN AXBLA UP06 6
stack FIN INNER UP07 1
stack FIN INNER UP07 2
stack FIN INNER UP07 3
stack FIN INNER UP07 4
stack FIN INNER UP07 5
stack FIN INNER UP07 6
stack FIN INNER UP07 7
stack FIN INNER UP07 8
stack FIN INNER UP07 9
stack FIN INNER UP07 10
stack FIN INNER UP07 11
stack FIN INNER UP07 12
stack FIN INNER UP07 13
stack FIN INNER UP07 14
stack FIN INNER UP07 15
stack FIN INNER UP07 16
stack FIN INNER UP07 17
stack FIN INNER UP07 18
stack FIN INNER UP07 19
stack FIN INNER UP07 20
stack FIN AXBLA UP08 1
stack FIN AXBLA UP08 2
stack FIN AXBLA UP08 4
stack FIN AXBLA UP08 5
stack FIN AXBLA UP08 6
stack FIN AXBLA UP08 3
stack FIN GASPLE1 UP09 1
stack FIN GASPLE1 UP09 2
stack FIN PLUG1 UP10 1
stack FIN EMPTY UP11 1
stack FIN EMPTY UP11 2
stack FIN EMPTY UP11 3
stack FIN OUTLET UP12 1
stack FIN OUTLET UP12 2
stack FIN OUTLET UP12 3
stack FIN OUTLET UP12 4
stack FIN OUTLET UP12 5
stack FIN OUTLET UP12 6
stack FIN OUTLET UP12 7
stack FIN OUTLET UP12 8
stack FIN OUTLET UP12 9
stack FIN OUTLET UP12 10
id: user-defined id of the vertical stack of homogeneous mixes;mixid: user-defined id of the homogeneous mix of isotopes filling the node if the stackid(should appear in themixcard);pipeid: user-defined id of the pipe (should appear in thepipecard);pipenode: index of the node inside the thermal-hydraulic pipe defining the node of the stackid.
Note: the stack represents a subassembly of the core. The axial nodalization of the stack is defined by linking every node of the stack with a pipe node.
tlife : Prompt neutron lifetime
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
# Prompt neutron lifetime
#---- ----1---- ----2---- ----3---- ----4---- ----5---- ----6---- ----7---- ----8---- ----9---- ----0----
##### tlife(s)
tlife 0.0005
tlife : prompt neutron lifetime (s).