2.8.2.1. Block 1 — INPCOM — Channel-Independent Options and Integer Input¶
NCHAN
1
Number of core channels. Maximum = 22000. (not to be confused with
the bypass channels of PRIMAR-4). NCHAN
must be less than or equal
to NCH from the data allocation record.
IDBUG0
2
Channel independent debug flag.
IFUEL1
3
Number of fuel types (Max. = 8).
ICLAD1
4
Number of cladding types (Max. = 3).
IPLUP
5
Fission gas plenum location:
IPROPT
6
ITKEL
7
Temperature scale for SSPRNT and TSPRNT print routines and TSPLOT plotting routine.
IPOWER
8
Power driver option.
IPOWOP
9
NPK
10
Reactor neutronics option.
MAXSTP
11
Maximum number of main (power and reactivity) time steps in transient calculation.
IPO
12
IPOBOI
13
Number of main (power and reactivity) time steps between full printouts after IBLPRT
or coolant boiling.
IBLPRT
14
NSTEP
15
Restart file save option. For any nonzero value of NSTEP
, the restart file is saved at the end of the steady-state calculation and when the transient simulation ends with either the maximum problem time, TIMAX
, or the maximum number of time steps, MAXSTP
.
NSTEP
main time steps during the transient, in addition to saving the restart file following completion of the steady-state and transient simulations.NDKGRP
17
Number of decay heat groups. 0 ≤ NDKGRP
≤ 24
The number of decay heat groups defined for any given curve may not exceed NDKGRP
(except as noted below for NDKGRP
= 0) but may be less than NDKGRP
. This allows standard curves to be combined with user-supplied curves with a lower expansion order.
Decay heat calculations can be disabled by setting NDKGRP
= 0 even if other decay heat input is present.
NPREAT
18
NPRES
19
IFLOW
20
NONEU0
21
Reserved for space-time options.
NT0TAB
22
MULSTR
23
ICLCMP
24
INEDIT
25
Input edit option.
IYLD
26
Cladding flow stress formulation.
YLDTAB
.IPRION
27
PRIMAR-4 option.
IMELTV
28
Axial extent assumptions for the molten cavity pressure calculation.
INAS3D
29
NCLADM
30
Not currently used.
ICREXP
31
Control rod drive expansion option
ICRDDB
flag to control output is recommended).IXSTPC
32
IXSTPF
33
Controls when the DEFORM computed axial expansion calculation is stopped based on fuel melt percentage molten.
IXSTPF
<= 100).IDBPWI
35
IRADEX
36
Radial expansion feedback option.
Simple radial expansion model
Detailed radial expansion model
KFAILP
37
NCPLEV
38
Switch from PLUTO2 to LEVITATE when NCPLEV
axial cladding nodes have exceeded the cladding liquidus temperature.
Suggested value: 3.
NCPLEV
= 0: Do not switch from PLUTO2 to LEVITATE due to cladding melting.
A switch from PLUTO2 to LEVITATE occurs automatically if all fuel and cladding in the pin are molten in any axial node.
NFUELD
39
Number of dollars of fuel reactivity to terminate the calculation. Recommended value: -5. | | PL,LE |
IAREXT
40
Controls radial extent of integration when calculating the plain strain axial expansion.
NOREAC
41
Reactivity print option.
NOREAC
main time steps.NSLEEX
42
Number of fully molten hexcan cells in a subassembly to terminate the calculation.
NSRMTB
43
Not currently used.
INRAEJ
44
CIPINJ
)NPOWDK
45
Number of power curves or sets of user-defined decay heat curves used. 0 ≤ NPOWDK
≤ 5
For IPOWER
= 0, NPOWDK
defines the number of user-defined decay heat curves to expect in the input. (Do not count any built-in ANS standard curves that are used in the problem.) NPOWDK
should be zero when using the original (Version 1.0) decay heat input.
For IPOWER
= 1, NPOWDK
defines the number of user-supplied power vs. time tables. This usage is unrelated to the decay heat model.
NPDKST
46
Number of entries in the POWLVL
vs. POWTIM
and PWLVL2
vs. PWTIM2
tables for performing steady-state initialization of the decay heat precursors.
0 ≤ NPDKST
≤ 8
If NPDKST
= 0, infinite steady-state irradiation is assumed for all decay heat regions regardless of the input in POWLVL
/POWTIM
and PWLVL2
/PWTIM2
.
ICHUNK
47
ILUBLK
48
INAPN
49
Sodium vapor pressure treatment.
NOEQPN
50
LOCATIONS 51-54 USED ONLY IF |IRADEX| > 3
NSUBTC
51
Total number of subassemblies in the active core region, including control and internal blanket subassemblies. Used for calculating the core radius in the radial expansion reactivity feedback calculation.
MTGRD
52
Support grid material, used for calculating the thermal expansion of the grid during a transient.
MTACLP
53
Above-core load pad material. Used for calculating the thermal expansion of the above-core load pad during a transient.
MTTLP
54
Top load pad material, used for calculating the thermal expansion of the top load pad during a transient.
MODEEX
55
Axial expansion option.
JREEXT
56
IFT19
57
Not currently Used.
IREACT
58
Reactivity feedback model option.
LOCATIONS 59-65 USED ONLY IF |IRADEX| > 3
NSUBTR
59
Total number of subassemblies in the reactor, including drivers, radial and internal blankets, control assemblies, radial reflectors and shields.
NRRNGS
60
Number of restraint rings in core restraint design.
MTRRAC
61
Material of the restraint ring at the above-core load pad elevation.
MTRRT
62
Material of the restraint ring at the top load pad elevation.
MTRFAC
63
Radial reflector and/or blanket above-core load pad material.
MTRFT
64
Radial reflector and/or blanket top load pad material.
IROPT
65
Assumption for low power-to-flow ratios.
JCRIND
66
For use with EBR-II reactivity model only.
This is the lowest node in which the control rod is present in the special EBR-II control rod feedback model. Sums then run from JCRIND
to the top of S/A.
ID2O
67
IDNFLW
68
IPLTSG
69
Number of main time steps between saving plot data for the steam generator model.
IBOP
70
Balance of plant modeling option.
When the balance of plant model is activated, steam generators do not participate in the null transient.
ICRDDB
71
Control rod drive expansion print option.
ICRTMP (K)
72-74
ICRNOD (K)
75-77
Number of axial nodes per section of CRD.
NSEGCR
78
Number of PRIMAR4 segment representing control rod assemblies.
ICHCHT
79
Not currently Used.
NOEQLE
80
Controls the pressure in the molten cavity at the time of LEVITATE or PLUTO2 initiation.
PCFAIL
> 1.0, the pressure is set equal to PCFAIL
.If LEVITATE or PLUTO2 are initiated after PINACLE, the pressure is always equal to the PINACLE pressure and NOEQLE
is not relevant.
MTCB
81
Core barrel material.
KDEBUG
82
KEBRS1
83
Main time step number to turn EBR-II routine debugging on.
KEBRS2
84
Main time step number to turn EBR-II routine debugging off.
IDBDKH
85
Reserved for future decay heat modeling.
NULLD3
86
Number of flux shape calculations in addition to the initial cold solution in the steady state power distribution/thermal hydraulics iteration for NPK
> 0.
ISSNUL
87
NOFDBK
89
Transient reactivity feedback option for NPK=0.
IBOPLT
90
Balance-of-plant plotting file option.
ISIMPG
91
Graphical interface for simulator application.
KHDBK
92
KFIRR
93
KDENBU
94
Option for correction of U-Pu-Zr alloy fuel theoretical density for the presence of fission products, based on average fuel burnup and fabricated composition (See BURNFU
, WUREF
, WPUREF
, WZRREF
). Only for IMETAL
= 2, IRHOK
= 1, and IFUELM
= 0.
IFIT (K)
95-100
Input table look-up options.
IFIT
:
K:
IPIC
101
PINACLE/LEVITATE pin picture plot flag.
IBOWTP
102
Temperature flag in EBR-II bowing reactivity.
ITARGE
103
Not currently used.
IEMGEM
104
FFTF Gas Expansion Module (GEM) model.
IPBDEN
106
MSTPL2
110
KTREAT
112
TREAT modeling flag.
KQSCRA
113
Modeling option for external source with scram.
KPROPI
114
ISCH
115
Coolant channel thermal-hydraulics model option.
ISKDOT
116
Input data printing option.
NLINMX
117
Printed output line limit, in thousands of lines, for the printed output file.
No longer used.
ICLPRP
118
Coolant material properties used in the core and all of PRIMAR except for the DRACS loops.
APROPI
.Note: If ICLPRP
> 0, then ICLPRP
overrides INAS3D
, ID2O
, IPBDEN
, and KPROPI
. See INAKDR
for the DRACS loop properties.
IFT1TM
119
Output flag for printing maximum core channel temperature data to auxiliary output file MaxTemps.txt.
IFT1TM
time steps.IVIS3D
120
3D visualization data output flag. Normally used for detailed sub-channel output.
IVIS3D
time steps.INPDU2
121-250
Not currently used.