pc based vpi manual 1994
TRANSCRIPT
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PC Based VPI odules:
User's Guide
1tMbt1lt
Centre
or
Nuclear
Studies
P o Nilore, Islamabad
Pakistan
October, 1994
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PC-Based VPI Modules: User's Guide
Page
0)
O\i\f
TO USE
PC-BASED VPI
MODULES
Centre for Nuclear
Studies
(CNS) Version
Nasir M Mirza
Center
for Nuclear
Studies
P.O. Nilore, Islamabad
Pakistan
October,
1994*
*
These
lectures \vere delivered
to J\ l.S.
Nuclear Power Engineering
Course
a t KANUPP
Insti tute
of Nuclear Power Engineering, Karachi.
Centre for Nuclear Studies, P.O. Nilore,
Islamabad,
Pakistan.
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PC-Based VPI Modules: User's Guide
Page (1)
Sample Problem for the VP Modules
Initially the
VPI
modules were developed for I
BM
and CDC machines, in winter of 1980
during the course of lectures on operational physics of Power Reactors
at
Triste, Italy, Dr. B.
Carmignani told the audience. These codes were developed at Nuclear Engineering Department
at
Virgina Polytechnic Inistitute and
State
University,
US L1
under
the
guidence of Dr. Milton
C. Edlund. These codes were brought by Dr. M.R. Haroon at CI\JS and Subhan
Gul
was asked
to prepare a talk on ustility of these codes. Codes were made functional at CNS in 1983.
As
we
all know, code users have to spend most of their time figuring
out
accurate
format for various inputs. All the syntex errors occur due
to
wrong formats used in input data
files. Also, the VAX Computer system or any large computer has CPU time distribution as
a function
of
users.
If
codes are being borrowed from same source directory, then code use
has many flaws. To circumvent
all
these difficulties, We
at
CNS
have ported these codes
to
Personnal Computers after minor changes. And every module has now a input data generator:
a program that will ask question and prepare a data file from answers. Codes now require
very little effort on data input. Both
the
interactive and non-interactive data generators are
available. These generators have been developed
at
CNS using FORTRAN-n. For each
VPI
Module a particular generator will generate a data
file
for variable input data which
will
be
compatible with the code.
You
can now patch a graphic routine
of
your choice to see the
output directly. We have labelled these codes as CNS
ersion
of VPI modules. These sections
aim
at
answering how
to
use these (CNS version) modules.
To illustrate the use of the VPI modules this report describes the application of these
(CI\JS
Version) codes for generation of group constants, group fluxes, flux distribution, reaction
rates and the integral parameters such as K-effective of a typical Pressurized Water Reactor
(PWR). As a sample problem we have choosen the Turkey Point Reactor operating
at
Florida,
USA. The schematics of the pressure vessel are shown in Fig. 1 The main design parameters
of this reactor are presented in Table 1
The reactor core
is
a three-region cycled core consisting of 158 fuel assemblies shown
l l
Fig. 2 with 42 Rod Cluster Control (RCC) assemblies. The fuel assemblies are divided into
three concentric regions having approximately equal volume with 2.28, 2.43 and 2.73 weight
percent w/o) enrichment
in the
center, intermediate and outer regions, respectively. Reflector
and thermal shield are around these regions. These are shown in Fig.
2.
The fuel rods are
cold worked Zircaloy tubes containing uranium dioxide fuel. The fuel assembly (Fig. 3)
is
of
the
can-less type with the basic assembly consisting of
RCC
guid thimbles welded to the grids
and the top and bottom nozzles. The active fuel length of the core is 289.56
cm
(114 in) and
the equivalent diameter of the core is 303.53 em (119 in)
The core elements have been assumed
at
following conditions: control rods withdrawn,
cold, clean, without boron. Also an equivalent fuel cell which differs slightly from the actual
eel
has been used in these calculations. A comparison of these cells is shown in Fig. 4.
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PC-Based VPI Modules: User s Guide
Page 2)
There
are 225 such cells
but only 204
are
actual fuel
cells.
The rest of 21
fuel cells have
been
assumed
to be water
holes
although they contain RCC and in-core instruments
in
20
and one
cell respectively.
In
order to simplify these calculation we
have
distributed the water of 21
holes
uniformly
in
all the 204 fuel cells and effect of structural materials has been ignored. Similar calcu
lations
were done
for reflector
and
thermal shield
zones
of the
core.
These
codes
consider
homogeneous regional
group constants.
All
these codes are
contained
in
a
compressed
file labelled
as
VPI.EXE.
Copy
this file from
the given floppy diskette to the main c-directory of your computer.
Type
VPI,
and
the
press
the return key. It will
explode
itself into various files after generating a sub-directory, VPI. It
will contain
REP.EXE
REPGEN.EXE, REP.DAT and RAP.RES FILES for
REP
code. For FAR-
CON
Code
there
are
FARCON.EXE, FARGEN.EXE FARCON.DAT,
and
FARCON.RES files.
Check that directory
has
DISFAC.EXE, DISGEN.EXE, DISFAC.DAT
and
DISFAC.RES files
for
code
DISFAC. Also
you
will have
SLOWCOI\J.EXE
SLOGEN.EXE, SLOWCON.DAT,
and
SLOWCON.RES files for
code
SLOWCON. The
code
ODMUG
is
composed of ODMUG.EXE,
ODGEN.EXE, ODMUG.DAT and ODMUG.RES files. Moreover the REP and
FARCON
have
fixed data files REP.L1B
and
FARCON.L1B respectively.
Users
need not change these fixed
data files.
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PC-Based VPI Modules: User's Guide
Page
3)
Table
1:
Typical WR
Core
Design Parameters
Active Portion of the Core
Diameter of the corea (in)
119.5
Active Height of
the
core (in)
144.0
Length to diameter ratio
1.205
Total cross section area (ft
2
)
78.3
Fuel Assembly
Number of fuel assemblies
~
Rod
arrays
15
x 15
Rods per assemblyb 204
Rod
pitch (in) 0.563
Overall dimensions (in)
0.426 x 8.426
Total weight of U
2
(pounds)
179,000
Total weight (pounds)
226,000
Number of grids per assembly
8
Fuel Rods
Number of fuel rods
32,028
Outer diameter of fuel
rod
(in)
0.422
Gap (in)
0.0065
Clad
thickness (in)
0.0243
Clad material
Zircoloy
Fuel Pellets
Material
Density (Enrichment
w/o):
Inner region
2.28%
Intermediate region
2.43%
Outer region 2.73%
Diameter of fuel pellets (in)
0.367
Length of fuel pellet (in) 0.60
Rod
Cluster Control
Assemblies
Nuetron absorbei(5%, 15%,
80%)
Cd-In-Ag
Cladd type (55-304) Stainless steel
Clad thickness (in)
0.019
Number of clusters
41
Number of control rods per cluster
20
Core
Ditnensions
Core barrel inner/outer diameter (in)
133.5/137.25
Thermai shield inner/outer diameter (in)
1411
147
5
a.
All
dimensions for Turkey Point Reactor are at cold conditions.
b Twenty one rods are omitted: 20 rods are control and one
is
for the instrumentation.
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PC-Based VPI Modules: User's Guide
Page 4)
Resonanc es Escape Probability alculations Us-
ing REP
ode
The REP code at present can only be used for a single problem at a time. Such declaration is
made through input card by letting J\JCAS (number of cases) put equal to one.
In
this code
the resonance escape probilities are calculated considering the actual cell (Shown in Fig. 4).
There is no resonance calculations for the reflectors and thermal shield zones of PWR. These
values are equal to one.
The code uses a fixed input data constituted by 54 cards or lines that contain the
resonance parameters for U-238. There are then seven cards containing weighting factors and
polynomial roots necessary for the Gauss-Hermite and Gauss-laguerre quadratures used to
evaluate
the 'l/J(e, 3)
and
J(e, 3)
functions respectively. This fixed data is stored in
REP.L1B
file.
The values
in
this data
file
are shown
in
Annexe-I.
Now check the sub-directory, VPI, for REPGEN.EXE, REP.EXE and
REP.L1B
files. The
REP.L1B
contains fixed data values
and we
have declared it as a library attached to the
REP
code. We
will
not change the name and data of this file (so it
is
fixed).
To run
this code on IBM-compatible PCs (286 and/or higher machines), first we have
to prepare a input data which can be changed according to our needs. Such data
file
is called
variable data
file I
usually
call it
REP. OAT). To generate this data
file
we have written an
interactive programme REPGEN and its executable
file
REPGEN.EXE is with you.
To run
this
programme type: REPGEN and then press the ENTER
key.
The programme will ask questions
and
you
have
to
type appropriate values
in
free format
on
screen. The code requires
REP.L1B
as a
fixed
data
file.
Check the directory for this
file.
The REPGEN
will
read the data
you
typed as an answer to the question and store
in
the data file. At the end
it will
tell
you that
you
have supplied
all
the input required for the programme; your data
is
stored
in the file
so
and so. Then
it will
stop. You can edit
or
type the data
file
as per desire.
Then type, REP.EXE to run the
REP
code and press the ENTER or RETURN
key on
keypad. A massege
will
appear on screen:'PlEASE ENTER THE
FiXED
1f\IPUT DATA
FILE
NAME:'. Write the name
REP.L1B.
Then press the
RETURN key
and it will ask: 'ENTER
TH
E VARIABLE
DATA
FilE NAM E: '. Type the name of
file you
just created with REPGEN
say REP. OAT (if your data is in
file REP
OAT). Then another massege
will
appear on the
screen:'PlEASE ENTER THE OUTPUT
FILE
NAME'. You are supposed to write the name
of file in which
you
want to store the output. I usually write REP.RES (RES for result files).
Then press the ENTER key and in a few seconds
you
wili get a prompt that programme has
successfully completed itself.
You
can see the result by typing the REP. RES file.
You can change the REP.
OAT file
directly or
run
the REPGEN for
new
data values for
other regions of the core. Remember you can change the variable data file but never attempt
changes
in the REP.L1B
type
file. All
file
having
end
names as
LIB
are fix-data files.
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Page 5)
3
Fast
Group
constants Generation
Code
FAR-
CON)
This code
is
available on Pc. The FARCOI\J
CI\JS
Version) uses a library of cross section data
for 14 isotopes. It is read as a fixed input data only once at the beginning of the program run.
The fixed and variable data is shown in Annexe-I. Procedure to run this code is similar to the
method explained for
REP
code. First check the sub-directory, VPI, for the FARCON.EXE
and FARCON.DAT,
FARCON.L1B
and FARGEN.EXE. The variable input data preparation can
be done by using FARGEN.EXE.
Run
this data generator. It will ask you, where to store the
data.
Tell
the code
that you
want data file by name of FARCON.DAT. Then the code
will
ask
about data values. Enter them as per question. It will
allow you
to modify the card after all
values in one card have been entered. At the end, it
will
tell
you
where it has stored the data
and what to do next.
Yay
can
run FARCON
code by typing FARCON. It will ask the same type of question
as the REP code does ask. ENTER the appopriate answer.
It will
rquire fixed data library
FARCON.L1B and variable data file FARCON.DAT. It will output the results and write them
in file of your choice I usually label the output file FARCOI\J.RES).
4
Disadavantage Factor
Generation
Code DIS-
FAC)
The disadva ntage factors for various regions of the Pressu
rized
Water Reactor
ca
n be calculated
using this code. It
is
necessary to input macroscopic cross sections for Two regions of the cell.
i.e. fuel and cladding/moderator regions. For this test run the cross sections were obtained
from the
BN
L-235. The sample input data for Turkey Point Reactor
is
given
in
Annexe-I.
ThIS code is available on Pc. The
DiSFAC
CI\JS Version) is made up of DISFAC.EXE
and DISGEN.EXE. The sample data
is
stored as DISFAC.DAT and sample test results are
in
DISFAC.RES. It is read input data at the beginning of the program run. The variable data
is shown
in
Annexe-1. Procedure
to run
this code is similar
to
the method explained for REP
code. First check the sub-directory, VPI,
for
*.EXE files.
The variable input data preparation can be done by using DISGEN.EXE.
Run
this data
generator. It
Nill
ask you, where to store the data. Tell the code that
you
want data
file by
name of DISFAC.DAT. Then the code will ask about data values. Enter them as per question.
It will allow
you
to modify the card after
all
values
in
one card have been entered.
At
the end,
it will tell
you
where
it
has stored the data and what to do next.
The executable
file
for the code
DISFAC
is DISFAC.EXE and sample test result is stored
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PC-Based VPI Modules: User's Guide
Page (6)
n DISFAC.RES
file.
5
Slowing
Down
and Thermal
Group
Constant
Generation
Code SLOWCON)
The PC based CNS-Version of SLOWCON
is
composed of SLOWCON.FOR, SLOWCOI\J.EXE
and SLOWCON.DAT files. This code uses only variable data that the user provides to it. The
cross section library has been made as a part of the code and
is
arranged in subrountines. As
it
can be seen from the input data shown
in
Annexe-I,
the
atomic densities
in FARCON
and
SLOWCON are different. It depends on the fact that
the
atomic densities
for
the SLOWCON
were obtained from the atomic densities used in FARCON multiplied by the disadvantage
factors obtained from the
DISFAC
code. The procedure adopted
in
the modification of number
densities was following. The moderator isotope densities were multiplied
by
the disadvantage
factor and the cladding densities were multiplied by the disadvantage factor and a ratio of
R
fue
Reel .
First check
the
sub-directory, VPI, for
the
SLOWCOI\J.EXE and SLOWCON.DAT, and
SLOGEN.EXE. These files form basis for PC-based SLOWCON code.
It
uses
an
input data
at
the
beginning of the program run. The sample variable data for Turkey Point Reactor
is
shown
in Annexe-I. Procedure to run this code is similar to the method explained for REP code.
The variable input data preparation can be done by using SLOGEN.EXE.
Run
this data
generator.
It
will
ask
you
where
to
store the data.
Tell
the code
that
you
want data
file
by
name of SLOWCON.DAT. Then the code will ask about data values. Enter them. The code
SLOGEN
will
allow you
to
modify
the
card after all values
in
one card have been entered.
Also, the data can be prepared for many regions (inner, middle, outer etc.,). At the end,
it
will
tell
the
name of input data
file
prepared
by
the code.
6 One
Dimensional Diffusion
Theory
based Calcu-
lations ODl\1UG)
This code uses the multigroup diffusion theory
to
calculate the multiplication factor for com
plete reactor system. t also provides the fission reaction rate, fluxes and region-wise group
fluxes. This code needs boundry conditions i.e. left and right
flux
and current conditions and
geometry being used. The group constants for fast, epithermal group generated by FARCON
and thermal constants
by
SLOWCON form the input for this code.
The
PC
based CNS-Version of ODMUG
is
composed of ODMUG.FOR, ODMUG.EXE
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VPI Modules: User's Guide
Page
(7)
and ODMUG.DAT files. Procedure to run this code
on
PCs is similar to the method explained
for
REP code.
The user has to input diffusion coefficients, absorption cross sections, removal cross
sections, poison cross section and
the
values
of
neutrons released per fission in various energy
groups for different regions of the reactor. These are generally the result of FARCON and
SLOWCON.
Also
transverse buckling, power levels and core dimensions are needed for this
code
to
run. The schematics of the reactor regions
is
shown in
Fig. 5. If
one wishes
to
perform
a poison search then desired value of
j f
and convergence criterion for the poison search
will
also be needed. The input data for typical problem is given
in
Annexe-1. The sample input
specifications
for
the fuel cell are given in Table 2. For three different zones of enrichment the
number densities are calculated separately. These values are illustrated in Table 3 4 and
5.
The ODMUG is available on
Pc.
The ODMUG (CNS Version) read an input data only
once at
the beginning of the program run.
The
variable data for Turkey Point Reactor
is
shown
in
Annexe-I. Procedure
to
run this code
is
similar to the method explained for REP and
FARCON
codes. First check the sub-directory, VPI, for the ODMUG.EXE and ODMUG.DAT
and ODGEI\J.EXE. The variable input data preparation can be done by using ODGEN.EXE.
Run this data generator. It will ask you, where to store the data. Tell the code
that
you want
data file by name of ODMUG.DAT. Then the code will ask about data values. Enter them
as per question. t
will
allow you to modify the card after all values in one card have been
entered. At the end, it will tell you where it has stored the data.
Table
2: The Sample Reactor Cell Specifications
(To be
Used
as LEOPARD
INPUT)
Cold
Dimensions
Pellet Outer radius (in) 0.1840
Clad Inner radius (in) 0.19
clad Outer radius (in) 0.2114
Square pitch (in) 0.56
I Engineering Specifications
Fuel tem peratu re (degree
F
1200
Clad temperature (degree F
620
Moderator tem peratu re (degree F
572
Pressure (psia)
2250
"
I,
Power(watts/cm of core height)
190
I'
Weight fraction
of
U-235 in U
0.03
il
Fuel
density
(91%
of 10.96 gm/cm
3
)
9.974 .
I'
i Clad material
Zircoly (Zr-4) 'II
i
As s emb l y
PWR,
~
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Based
VPI
Modules: User s Guide
Page 8)
Ta
ble
3:
The Atom Densities( no.
per
barn-em) for
the
Fuel Cell
with
2.28
w0 enrichment.
Fuel I Cald I
Moderator
I Cell
Volume Fraction 0.30243 0.09766
0.5999
1.0
Hydrogen
-
-
0.6700 0.0402
Oxygen 0.04597
-
0.0335 0.034998
Zirconium
-
0.0378
-
0.003692
U-235 0.00052
- -
0.000157
I
U-238
0.02246
- -
0.006794
I
Table
4: The Atom Densities(no.
per
barn-em) for
the
Fuel
Cell with 2.43 w o enrichment.
Fuel Cald
Moderator
Cell
Volume Fraction 0.3024 0.09766
0.5999 1.0
Hydrogen
-
Oxygen
0.0460
Zirconium
-
U-235 0.00057
U-238
0.02242
-
-
0.0378
-
-
0.6700
0.0402
0.0335
0.0340
-
0.003692
-
0.000171
-
0.006780
Table 5:
The atom densities (atoms
per
barn-em) for the
Fuel
Cell
with 2.73 w
0
Enrichment
Fuel
Cald
Moderator
Cell
Volume Fraction
0.3024 0.09766 0.5999 1.0
Hydrogen
Oxygen
Zirconium
U-235
U-238
-
0.04548
-
0.00063
.
0.02211
-
-
0.0378
-
-
0.6700
0.0350
-
-
-
0.0402
0.03385
0.00369
0.00019
0.00667
I
These
notes were
prepared from the lecture handouts
delivered
by
B.
Carmignani in the
following
conference as
SMR/8/11-11.
We
gratefully
acknowledge Dr.
Carmignani
and
the
following:
WiNTER COU.EGE OF NUCLEAR PHYSICS Af\JD
REACTORS
COURSE
ON
OPERATIONAL PHYSiCS
OF
POWER
REACTORS
3-
28 March
1980
I N T R N T I O ~ J L
CENTRE
FOR
THEORETICAL
PHYSICS,
TRISTE (Italy);
P.O. B. 586; MIRAMARE STRADA COSTIER.A II;
TELESROSES:
2T42HI/2/3 153, CABLE CENTRATOM TELEX 460392
I.
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Core
Therma
Shield
Control
Rods
Pressure
vessel
~
~ l l l l l l l l i Ref lector
Coolant Path
Page 9)
PC-Based
VPI
Modules: User s Guide
Hot
Leg
Coolant
Outlet
====
Cold
Leg
Collant Inlet
Fig 1 Pressure Vessel
and
Coolant Flow for a Typical
PWR
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udear
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PC-Based
VPI Modules: User s Guide
Page 10)
Fuel
ssembly
Thermal Shield
Core affle
Core Barrel
nl
O r = 2.
wi 0
'
r .
w o
f l
r
:: 2.73 w 0
Fig 2 Reactor
Core Cross
Section
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PC-Based VPI Modules: User s Guide
Page
11)
-
Fuel Rod
Water Hole
igo 3 Fuel
Assembly Cross Section
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PC-Based
VPI
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Page 12)
1
5
em
_
_
Fuel
Moderator
_.43 em
_
0.466 em
(a)
b)
0.536
em
0 847 em
Fig. 4 Actual
a) and the computed
b) fuel
cell
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Page 13)
Fuel r 2 28
w/oII
Fuel r 2 43
w/o
uel r
2.73-
w/o
eflector
Thermal
shield
88 104
124 02 ;.,; .:iY'l_----I
151 765
In
169 645 in 4
173 in
Fig. 5 The reactor schematics for ODMUG
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User s
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Page
(14)
ANNEXE-I
INPUT DATA FOR PC-BASEDVPI IVIODULES
Centre
for
Nuclear Studies (CNS) Version
Nasir M.
Mirza
October, 1994.
Centre for Nuclear
Studies,
P.O. Nilore, Islamabad,
Pakistan.
-
8/10/2019 Pc Based Vpi Manual 1994
17/33
-
8/10/2019 Pc Based Vpi Manual 1994
18/33
PC-Based
VPl
Modules: User's Guide
Page 16)
c
-
C REP
INPUT
D T
for
Turkey Point Reactor
C
This data
is
s tored
in REP.LIB
f i l e . O
not
change
C
the
name
or the data.
of
t h i s f i l e
c FIXED
INPUT
D T FOR
REP CODE
[eNS] VERSION
Oct, 1994)
c
.67
E+011.52
E-032.26
E+04
2.1
E 18.9
E-033.294
E
4
3.69
E 13.25
E-024.016
E 4
6.63
E 12.5
E-021.
979 E 4
8.13
E 12.1
E-032.5189E
3
9.0
E
19.0
E-051.055
E 2
1.025
E
26.5 E-021.
843 E 4
1.165
E
21.5
E-028.466
E 3
1.456 E 28.0
E-045.632
E 2
1.662
E 23.5
E-031. 963
E 3
1.896 E 21. 35
E-011.
162 E 4
2.085 E 25.5
E-028.628
E 3
2.376
E
23.2
E-026.198
E 3
2.645
E
22.3
E-049.118
E 1
2.74
E 22.7
E-024.972
E 3
2.91
E
21.9
E-023.899
E 3
3.155
E
21.0
E-033.265
E 2
3.48
E
24.5
E-024.837
E 3
3.77
E 21.5
E-033.969
E 2
3.985
E 21.0
E-021.888
E 3
4.11
E
21.7
E-022.589
E 3
4.35
E
21.4
E-022.17 E 3
4.55
E
27.0
E-041.583
E 2
4.64
E 27.0
E-031.243
E 3
4.79
E 24.5
E-038.406
E 2
4.9 E 21.0
E-032.076
E 2
519.
E
03.7
E-023.013
E 3
5.36
E
25.4
E-023.337
E 3
5.57
E 21.0
E-031.826
E 2
5.81
E
24.2 E-022.826
E 3
5.96
E 26.6
E-023.1824E 3
6.05
E 26.0
E-041.025 E 2
6.21
E
23.9
E-022.571
E 3
6.29
E
29.0 E-031.109
E 3
6.62
E
21.25
E-013.286
E 3 .
6.8
E
21.3
E-031. 922 E 2
6.95
E
25.3
E-022.5587E
3
Centre
for
Nuclear Studies, P.O. Nilore, Islamabad,
Pakistan.
-
8/10/2019 Pc Based Vpi Manual 1994
19/33
PC-Based VPI Modules: User's Guide
Page (17)
7.1
E
21.7
E-021.499
E 3
7.23 E
21.47 E-021.347
E 3
7.32
E 24.25 E-035.240 E 2
7.66
E
29.0
-039.105 E 2
7.82
E 23.0 E-033.619 E 2
7.92
E 21.1 E-021.016 E 3
8.25 E
26.0 E-022.238
E 3
8.55 E 21.3 E-012.561 E 3
8.59
E 26.0 E-022.150 E 3
8.67 E 22.2
E-032.465
E 2
8.96
E 21.3 E-031.4586E 2
9.09 E
29.0 E-022.249
E 3
9.28 E 23.7
E-021.685
E 3
9.4 E 21.95 E-012.456 E 3
9.6 E 21.9 E-012.4013E 3
9.83
E 21.0 E-031.035 E 2
9.96 E
24.0
E-012.465 E 3
c
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
C
- - - - - REP
INPUT DATA for Turkey
Point
Reactor
C - - - - - This data can be generated by running REPGEN.EXE
C - - - - - Then s tore i t as REP.DAT f i l e . You can change
C - - - - - the name or the data of th is f i l e
c - - - - - VARIABLE INPUT DATA FOR REP
CODE
[CNS]
VERSION
(Oct, 1994)
.308441115765
.401119929155 .218068287612 .0620874560987
.950151697518
D-02.753008388588
D-03.28259233496
D-04.424931398496
D-O
.183956482398
D-08.991182721961 D-12.13779347054 .729454549503
1.80834290174 3.401433697855 5.552496140064 8.330152746764
1.18437858379
D
11.6279257831378
D
12.1996585811981
D
12.9920697012274
D
2.0201828705 -2.0201828705 .9585724646
-.9585724646
.199532421
D-01
.199532421
D-013.936193232 D-013.936193232
D-019.453087205
D-O
c
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
1
VARIABLE
INPUT
DATA
FOR
REP
TEST
CASE
[nasi r
m.]
238.0
91.22
16.0 3.8
10.7
20.5
6.1
10.3
6.5 1.0 .00008616 .98
0.0246
O.
0.33362
0.10776 0.56863 293. 293. 0.466
0.0228
The
end
of the input data file for REP
code.
Centre for
Nuclear Studies, P.O. Nilore, Islamabad, Pakistan.
-
8/10/2019 Pc Based Vpi Manual 1994
20/33
-
8/10/2019 Pc Based Vpi Manual 1994
21/33
PC-Based VPI Modules: User s Guide
Page (19)
c FIXED INPUT DATA FOR FARCON CODE CNS VERSION [NASIR M.J
OCT
1994
c
t h i s data i s stored
in
FARCON.LIB. Do not change
the data or
the
c
f i l e
name.
C -
0.0 0.0 0.0
0.0
0.0
0.0
0.0
0.0 0.0 0.0 0.0 0.0 0.0
0.0
0.0
0.0470.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
0.2880.1030.0
0.0 0.0
0.0 0.0
0.0 0.0 0.0
0.0
0.0 0.0 0.0
0.0
0.6780.3880.2360.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
0.0
0.0 0.0
0.7970.6330.5600.3710.0 0.0
0.0 0.0
0.0
0.0 0.0
0.0 0.0 0.0
0.0
0.6040.5780.6650.6010.4570.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
0.3450.3830.5060.5580.5540.4670.0
0.0
0.0
0.0 0.0 0.0
0.0 0.0 0.0
0.1670.2000.2910.3640.4130.4330.4200.0
0.0
0.0 0.0 0.0
0.0 0.0
0.0
0.0720.0910.1410.1900.2360.2830.3190.3170.0 0.0 0.0 0.0 0.0 0.0
0.0
0.0290.0380.0620.0860.1150.1470.1830.2060.2040.0 0.0 0.0 0.0 0.0 0.0
0.0120.0150.0240.0360.0510.0670.0890.1070.1180.1110.0
0.0 0.0
0.0
0.0
0.0030.0060.0100.0140.0210.0280.0380.0490.0570.0580.0480.0
0.0 0.0 0.0
0.0 0.0
0.0030.0060.0080.0110.0160.0200.0250.0270.0240.0200.0
0.0
0.0
0.0 0.0 0.0 0.0 0.0040.0040.0060.0080.0100.0110.0100.0090.0020.0 0.0
0.0 0.0
0.0 0.0
0.0 0.0020.0010.0020.0020.0030.0030.0020.0 0.0 0.0
0.002050.002250.002900.004200.006750.011000:012000.012000.012000.012500.01450
0.018500.028000.05 0.0825
0.12
0.155 0.075 0.095 0.13 0.965 0.00215
0.0028 0.0036 0.0046
0.0059
0.0076 0.009750.0125 0.0161 0.0206 0.027 0.0347
0.540
1.000
1.785
2.865
4.55
6.098
7.21 7.48 7.79 7.93 8.78
8.13
8.52 7.44
8.78 7.35 7.15 6.35 5.80 6.40 7.25 6.25
6.25 6.25 6.25 6.25 6.25 6.25 6.25
6.25
6.25
6.20
6.20
0.0118
0.017
0.030 0.051 0.0818 0.117 0.147 0.163
0.167
0.174 0.184
0.187 0.184 0.177 0.179 0.178 0.160
0.150 0.134
0.135 0.151 0.150
0.138
0.138
0.138 0.138
0.138
0.138 0.138 0.138 0.138 0.136
0.136
0.0
0.0
0.0 0.0 0.0
0.0 0.0
0.0 0.0 0.0 0.0
0.0 0.0 0.0
0.0 0.0 0.0 0.0 0.0 0.0
0.0
0.0
0.0
0.0 0.0
0.0 0.0
0.0 0.0
0.0 0.0
0.0 0.0
0.388
0.564 0.778
1.04 1.37
1.81 2.33 2.95
3.65
4.40 5.06
5.59
5.98
6.26 6.48 6.64 6.66 6.69 6.69 6.73 6.74 6.76
6.79
6.81
6.83
6.86
6.88
6.89 6.93
6.94
6.96 6.91 7.15
1.17 1.43 2.02
2.72
3.61 4.77
6.21
7.93 9.90
12.1 14.2
16.0
17.4
18.4 19.1 19.7 20.0 20.1 20.1
20.2
20.2
20.3
20.4
20.4 20.5 20.6 20.6 20.7 20.8 20.8 20.9
21.0
21.8
0.0 0.0
0.0
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
0.0 0.0
0.0
0.0
0.0 0.0
0.0 0.0 0.0 0.0
0.0
0.935 0.985 1.19 1.80
4.73
2.77 6.76
3.10
3.13 3.15 3.19
3.27 3.35 3.44 3.52 3.64
3.64 3.64
3.64
3.64
3.64 3.64
3.64 3.64 3.64 3.64 3.64 3.64 3.64 3.64 3.64
3.60 3.60
Centre
for
Nuclear Studies, P.O. Nilore, Islamabad, Pakistan.
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PC-Based
VPI
Modules: User s Guide
Page (20)
0.122
0.123
0.138
0.184
0.413 0.477 0.581 0.631 0.390
0.396
0.401
0.408
0.416 0.427 0.438 0.451 0.458 0.460 0.460 0.460 0.460
0.460
0.460
0.460
0.460
0.460
0.460 0.460 0.460
0.460
0.460
0.455
0.455
0.0 0.0 0.0 0.0 0.0 0.0
0.0 0.0
0.0
0.0 0.0
0.0 0.0
0.0
0.0
0.0 0.0
0.0
0.0 0.0
0.0
0.0
0.0 0.0 0.0
0.0 0.0
0.0 0.0 0.0 0.0
0.0 0.0
1.
62 1.85
2.41 1.
85 3.15 4.17 3.43 3.98 4.72 4.91 5.09
5.56
5.56 5.56 5.56 5.56 5.56 5.56
5.56
5.56
5.56
5 56
5.56 5.56
5.56
5.56
5.56 5.56
5.56 5.56
5.56 5.56 5.56
0.311 0.393 0.455 0.373 0.497 0.725 0.745 0.849 0.962 1. 06 1.14
1.18 1. 24
1.24
1.
24
1.
24
1.
24
1.
24
1.
24
1.24 1. 24
1. 24
1.
24
1.
24
1.24
1.
24
1.
24
1.
24
1.24 1.24
1.
24
1.
24
1.
24
0.15 0.14
0.165
0.315 0.220 0.475 0.705 1. 03 1.57 2.21
2.93
3.68
4.55 5.55 7.30
9.40 12.1
15.5
19.9
25.5
32.7 42.1
53.5
69.5 89.0 113.0
146.0
186.0 239.0
305.0 384.0 518.0 669.0
0.0
0.0 0.0
0.0
0.0
0.0
0.0
0.0 0.0
0.0 0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0 0.0 0.0 0.0
0.0 0.0
0.0
0.0 0.0 0.0 0.0 0.0 0.0 0.0
0.0
0.0 0.0 0.0 0.0 0.0
0.0
0.0 0.0
0.0 0.0 0.0
0.0
0.0 0.0
0.0 0.0
0.0
0.0 0.0 0.0
0.0 0.0
0.0 0.0
0.0
0.0 0.0
0.0
0.0
0.0
0.0
0.0 0.0
0.0
0.0 0.0 0.0 0.0 0.0 0.0
0.0
0.0 0.0
0.0
0.0 0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0 0.0
0.0 0.0
0.0
0.0 0.0 0.0
0.0
0.0 0.0
0.575
1. 22 1. 68 1. 69
2.18 2.74 3.25 3.65
3.94 4.13
4.27
4.34
4.39
4.42 4.44 4.44 4.45 4.45 4.45
4.45 4.46
4.46
4.46
4.46 4.46 4.46
4.46 4.46 4.46
4.46
4.46
4.46 4.46
0.097 0.205
0.313 0.285 0.365 0.462
0.549
0.614
0.665 0.696 0.719
0.736 0.741
0.746
0.747
0.749 0.750
0.751 0.751
0.751 0.752 0.752
0.752 0.752 0.752 0.752
0.752
0.752 0.752
0.752
0.752
0.752
0.752
0.131 0.063
0.024 0.007 0.004
0.006
0.006 0.007 0.009
0.017
0.015
0.033
0.015 0.025 0.059
0.031 0.023 0.041
0.278
0.025
0.277
0.038
0.062 0.059 0.072 0.092 0.118 0.152
0.195 0.251 0.321
0.412 0.603
0.285 0.710
1.19 1. 65
1.88 2.33 3.06 3.36 3.58
4.49
4.30
14.7
5.78
7.50
16.0
10.6
11. 9
8.08 8.96
9.78 17 .2
10.65
10.3
10.3
10.3 10.3 10.2 10.2 10.2
10.2
10.2 10.2
10.2
0.010
0.026 0.043 0.060 0.069 0.085 0.121
0.122 0.131
0.183
0.160
0.352 0.204 0.270 0.586 0.387
0.434 0.292
0.324 0.353
0.625
0.384
0.371 0.369 0.369 0.369
0.369 0.369 0.369
0.369
0.369
0.368
0.368
1. 69
1.19
1.31
1.36 1.35 1.37
1.52
1.
74
2.04
2.24
2.93
3.49
4.05
4.68
5.57
6.60 7.76 10.0
12.9
20.7
21.8
32.6
39.0
37.0
45.5
45.5
59.4
59.4
24.1
24.1
14.7
14.7
82.9
0.601
1.
00
3.19
2.18 2.06 2.75 3.95
5.50
7.51
8.28
9.31
Centre for
Nuclear Studies P.O.
Nilore
Islamabad Pakistan.
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23/33
PC-Based
VPI
Modules: User s Guide
Page
21)
9.94
10.2
10.3
13.1 15.1 16.5 15.5 16.5 14.0 15.5 13.0
12.0 11.0
11.0 11.0 11.0
11. 0
11.4
12.0
12.6
11. 2
12.0
0.005 0.008 0.013 0.015 0.018
0.022
0.034
0.047 0.061 0.071
0.080
0.085 0.088 0.088 0.113
0.129 0.141 0.133 0.141
0.120
0.124
0.111
0.103 0.094 0.094 0.094 0.094 0.094 0.098
0.102 0.107
0.096
0.103
1. 69 1.19 1. 29 1. 32 1. 25
1. 21 1. 29 1.43 1. 63
1.87 2.18
2.51
2.87 3.30 3.95
4.65 5.27
7.00 9.00
13.9
14.5 22.0
27.0 26.5 26.9 26.9
32.5 32.5
12.4 12.4 11.3 11. 3 85.0
3.49 3.06
2.80 2.65 2.55
2.50 2.48 2.46 2.45 2.44 2.43
2.43 2.43
2.43
2.43
2.43
2.43 2.43
2.43
2.43
2.43
2.43
2.43 2.43 2.43 2.43 2.43 2.43 2.43
2.43
2. LI :3
2.43 2.43
1.83
0.935
0.935 0.820 0.575
0.175
0.135
0.165
0.225
0.295
0.370
0.465
0.550
0.640
0.850 1. 05 1.35 2.15 3.75
3.90
7.50 8.50
0.0 0.0 0.0
0.0
0.0
0.0
0.0
0.470
0.620 1. 09 1.15
0.601
1. 00 3.19
2.18
2.06
2.75 3.95
5.50 7.51
8.28 9.31
9.94
10.2 10.3
13.1 15.1 16.5 15.5 16.5 14.0
15.5 13.0
12.0
11.0 11.0
11.0
11.0
11.0 11.0
11. 11.0 11.
0
11.
0
0.005
0.008
0.013 0.015 0.018 0.022
0.034
0.047
0.061 0.071 0.080
0.085 0.088
0.088
0.113
0.129 0.141
0.133
0.141 0.120
0.124 0.111
0.103 0.094 0.094
0.094 0.094 0.094 0.098
0.102
0.107 0.080
0.080
1.83
0.93
0.91 0.765 0.45 0.035 0.0
0.0 0.0
0.0 0.0
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
0.0 0.0 0.0 0.0 0.0
0.0 0.0
0.0 0.0
0.0 0.0
3.56 3.08 2.80
2.61
2.51 2.42 2.38
2.38
2.38
2.38
2.38
2.38
2.38 2.38 2.38 2.38
2.38
2.38
2.38
2.38 2.38
2.38
2.38 2.38 2.38 2.38 2.38
2.38 2.38
2.38 2.38
2.38
2.38
0.973
0.585
0.607 0.510 0.157
0.140
0.125
0.160 0.224
0.285
0.350
0.420
0.505 0.610 0.730
0.414
0.006 0.011
0.014
0.018 0.023
0.029
0.038
0.049
0.063
0.080 0.103 0.132
0.170
0.218
0.280 0.488
0.553
0.570
1. 1 1.41 1.89 2.55 3.61 5.15
7.07 9.11 10.7
11.9
12.5
13.1
13.5 14.2
14.8
14.8 12.9
11.9 10.5
10.4
10.4
10.4
10.4
10 .4 10.4 10.4 10.4 9.67
8.97
7.89 7.89
0.008 0.013 0.018 0.023 0.030 0.035
0.050
0.065
0.080
0.093 0.102
0.107
0.111
0.114
0.120 0.125 0.125 0.109
0.101
0.088 0.088
0.088
0.088
0.088 0.088 0.088
0.088
0.088
0.082
0.076 0.076
0.066
0.067
0.965 0.570 0.575
0.445
0.0295
0.0 0.0
0.0
0.0
0.0
0.0
0.0
0.0 0.0
0.0
0.0
0.0
0.0
0.0 0.0
0.0
0.0
0.0
0.0
0.0 0.0 0.0
0.0 0.0
0.0 0.0
0.0
0.0
3.50 3.07 2.81
2.65 2.56
2.50 2.46
2.44
2.43
2.42
2.42
2.41
2.41 2.41
2.41 2.41
2.41 2.41
2.41
2.41
2.41
2.41
2.41
2.41
2.41 2.41
2.41
2.41
2.41
2.41
2.41
2.41
2.41
2.11 2.45 2.50
2.23
1.85 1.44 1. 07
0.71
0.417
0.209
0.085
0.031 0.003
0.0 0.0 0.0
0.0
0.0
0.0
0.0
0.0
0.0
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0.0
0.0 0.0
0.0 0.0 0.0
0.0
0.0 0.0 0.0 0.0
2.20
1.38
1.
97
1.
98
1.87
1.
76
1.81 1. 86
1.
94
2.03
2.28
2.84
3.23 3.44 3.59
4.80
5.28
5.95
9.85
15.3
16.8 30.7
36.5
92.0 82.0
30.0
60.0 78.0 180.0 54.0 54.0
80.0
66.0
0.680
1.
00
1 38 1. 70 2.28 3.45 4.80
6.24
7.61
8.87 9.88
10.4 10.9
11.4 12.4 12.9 13.3 11. 7 11. 0
11.0
11.0
11.
0
11.0
11.0
11.0
11.0
11.0
11.0
11.0
11. 0
11.0
11. 0
11.0
0.007020.010
0.013
0.0167
0.0239 0.0345
0.0532
0.0584 0.0695
0.0791
0.0855
0.0900
0.0944 0.101 0.107 0.111
0.105
0.0956 0.0926 0.0926 0.0926 0.0926
0.0926 0.0926 0.0926 0.0926 0.0926
0.0926
0.0926 0.0926 0.0926 0.0926 0.0926
2.20 1.83 1.96
1.
96
i .83
1.
67
1. 66 1. 67 1. 70
1. 79 1
95
2.15 2.28 2.35 2.40 3.15 3.40 3.75 6.10 9.30 10.0 18.0
21.0
58.0 34.0
16.0
36.0
40.0
102.0
6.16 6.16
4.0
48.0
3.74
3.40
3.19
3.06 2.99 2.94
2.91 2.90 2.89
2.88 2.88
2.87
2.87 2.87
2.87
2.87
2.87
2.87
2.87
2.87
2.87 2.87
2.87
2.87 2.87 2.87 2.87 2.87
2.87
2.87
2.87 2.87 2.87
2.06
1. 58
1.
67
1.
71
1.
63 1.
03
0.425
0.380
0.481
0.592 0.716
0.844
0.978
1.13
1.32
1.
55
2.13
3.25 5.00
7.50
11.0
15.0
9.00
0.0
9.50
19.0
15.0
22.5
24.5
33.5 60.0
150.0
500.0
0.570
1.
01
1.41 1.89
2.54
3.60
5.15 7.07 9.11
10.7
11.9
12.5 13.1 13.5
14.2
14.1 12.5
10.5 11.0 11.
0 11.0
11.0
11.0 11.0 11.0 11.0 11.0
11.
0
11.
0
11.
0
11.0 11.0
11.
0
0.006550.0102 0.0136
0.0182
0.0256
0.0365
0.0511
0.0677 0.0833 0.0951
0.103
0.108 0.112 0.116 0.119 0.111
0.0964
0.0859
0.0838 0.0838
0.0838
0.0838
0.0838 0.0838 0.0838 0.0838
0.0838
0.0838 0.0838 0.0838 0.0838 0.0838 0.0838
2.05 1.
55
1.
61
1.
59
1.39 0.78
0.20 0.095
0.0805 0.078
0.086
0.089 0.0725 0.03
0.0 0.0 0.0
0.0 0.0
0.0
0.0 0.0
0.0 0.0
0.0 0.0 0.0 0.0 0.0
0.0
0.0
0.0 0.0
3.74 3.40
3.19 3.06 2.99
2.94
2.91 2.90 2.89
2.88
2.88
2.87 2.87
2.87
2.87
2.87
2.87
2.87
2.87
2.87
2.87
2.87
2.87
2.87
2.87
2.87 2.87 2.87 2.87 2.87 2.87
2.87 2.87
2.20
1.
61
1.
66
1.83 1. 77 1.81
1.
91
2.16
2.67 3.42
4.25
5.15
5.64
6.48 7.39 8.31 9.10 10.3 13.3 18.8 25.7 34.7
42.7
50.0 61.5
85.0 194.0 190.0 275.5 191.
5
46.0
20.0
30.0
0.680
1.
00 1.38 1. 78
2.28 3.45 4.79
6.25
7.61
8.87
9.88
10.4
10.9
11.4 12.6
12.3
11.9 11. 2
11.0
11.0
11.0
11.0
11.0
11.0 11.0 11.0
11.0
11.0
11.0
11.0 11.0
11.0 11. 0
0.005650.0084 0.0116
0.0142
0.0191
0.0288 0.0401 0.0523 0.0638 0.0743 0.0827
0.0868 0.0914 0.0956
0.105 0.103 0.993
0.939 0.918
0.918
0.918
0.918
0.918
0.918
0.918
0.918
0.918
0.918
0.918
0.918
0.918
0.918
0.918
2.20 1. 60
1.65
1.80
1.
70
1.
70
1.
75
1.
95
2.40
3.05
3.75
4.50
4.85
5.55
6.30 7.00
7.50
8.30
10.6
15.3
21.0
28.8
35.5 38.5 47.5
65.5
149.0
143.0
225.0
167.5
34.5
17.3
21.6
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2.97
2.97
2.97 2.97
2.97 2.97 2.97 2.97 2.97
2.97 2.97
2.97
2.97 2.97 2.97 2.97
2.97
2.97 2.97 2.97 2.97
2.97
2.97 2.97 2.97 2.97
2.97 2.97 2.97
2.97
2.97
2.97 2.97
1. 96
1. 38
1.43
1. 59
1. 74
0.825 0.370
0.380 0.470
0.530
0.630
0.755 0.905
1.10
1.32
1. 55
2.13 3.25
5.00
7.00
7.00 7.00
7.50
9.50 5.00
6.50 5.00
5.00
6.50
14.5 15.0 16.6 9.10
0.570 1. 01 1.41 1.89
2.54
3.60 5.15 7.07 9.11 10.7 11.9
12.5
13.1
13.3 13.5
14.2
14.2
13.1
11.
5
11.0 11.
0
11.0
11.0
11.0
11.0 11.
0
11.0 11.0 11.
0
11.
0
11.0
11.0 11.0
0.006510.010 0.0135
0.0180
0.0254
0.0362
0.0507 0.0672 0.0826 0.0943 0.102
0.107
0.111 o. 1:15
0.118 0.118 0.113
0.102
0.935
0.0914 0.0914
0.0914
0.0914 0.0914
0.0914
0.0914 0.0914 0.0914
0.0914 0.0914
0.0914
0.0914
0.0914
1.
95 1.35 1.38 1.48 1. 51
0.575
0.145 0.095 0.07 0.015 0.0
0.0
0.0
0.0 0.0
0.0
0.0
0.0
0.0 0.0
0.0
0.0
0.0 0.0
0.0 0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
4.06 3.69 3.47 3.33 3.25 3.20 3.17
3.15
3.14
3.13
3.13
3.12 3.12 3.12 3.12
3.12 3.12
3.12
3.12
3.12
3.12
3.12
3.12 3.12
3.12
3.12 3.12
3.12 3.12
3.12
3.12 3.12
3.12
0.0232
0.1082 0.2103
0.2313 0.1803
0.1147
0.0648
0.0340 0.0171
0.0161
0.0
0.0
0.0 0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0 0.0 0.0 0.0 0.0
0.0 0.0
0.0
0.0
0.0
ZIRC-2
HYDROGEN OXYGEN BE
BoRON-l0
CARBON
S.S.-304 U-235
U-235 U-236
U-238
PU-239 PU-240
PU-241 PU-242
C
c
-
C FARCON INPUT
DATA for
Turkey
Point
Reactor [nasir i l l ]
.
C This
data
can
be generated
by
running
FARGEN.EXE .
C
Then s tore i t
as
FARCoN.DAT f i l e . You can change
.
C the name or the data
of t h i s f i l e
.
c VARIABLE INPUT DATA FOR FARCoN
CODE
[CNS] VERSION (Oct, 1994).
c -
5
TEST
CASE FOR TURKET
POINT
REACTOR
INNER
ZONE
[NASIR M.]
OCT
1994.
1 1
0.003692
0.0402
0.033998
0.0
0.0
0.0 0.0
0.0001567
0.0
0.0067938
0.0
0.0
0.0 0.0
1.0 1.0 1.0 1.0
1.0 1.0 1.0
1.0
1.0
1.0 1.0
1.0 1.0 1.0 1.0 1.0 1.0 1.0
.998
.996
.997 .995
.987 .987 1.0
.971
.962
1.0 .992
1.0
1.0
1.0 1.0
0.000255
999.
TEST
CASE FOR
TURKET
POINT REACTOR
MIDDLE ZONE
[NASIR M.]
OCT
1994.
o 1
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(24)
0.003692 0.0402
0.033999 0.0
0.0
0.0
0.0
0.00Oi709 0.0 0.0067796 0.0 0 .0
0.0 0.0
1.0
1.0
1.0 1 .0
1 0
1.0 1 .0 1 .0
1.0
1.0 1 .0
1 0
1.0 1.0 1.0
1 .0
1 .0
1.0
.998
.996
.997 .995
.987 .987
1.0
.971 .962
1.0 .992 1.0
1 0
1.0
1.0
0.000255
999.
TEST CASE FOR TURKET
POINT
REACTOR, OUTER
ZONE
[NASIR
M
J
OCT,
1994.
0 1
0.003692 0.0402
0.033850
0.0
0.0 0.0 0 .0
0.0001899 0.0
0.006687 0.0 0 .0 0.0
0.0
1.0 1 .0 1 .0 1 .0 1.0 1.0
1.0
1.0 1 .0 1 .0 1 .0
1.0
1.0
1.0 1 .0
1 .0
1 .0 1 .0
.998 .996 .997 .995
.987 .987
1.0 .971 .962 1.0
.992 1.0
1.0 1 .0 1.0
0.000255
999.
TEST
CASE
FOR TURKET
POINT
REACTOR, REFLECTOR
[NASIR
M ]
OCT,
1994.
0 1
0.00
0.0670
0.0335 0.0
0.0 0.0
0.0
0.00 0.0
0.00
0.0 0.0 0 .0
0.0
1 0
1.0
1.0 1 .0 1 .0
1 .0
1.0
1.0
1.0
1.0
1.0
1.0
1.0
1.0 1.0
1.0 1.0 1 .0
1.0
1.0 1 .0
1 .0
1.0
1.0
1.0
1.0
1.0 1 .0 1 .0
1.0 1.0 1 .0
1.0
0.000255
999.
TEST
CASE
FOR TURKET
POINT
REACTOR, THERMAL SHIELD
[NASIR
M ]
OCT,
1994.
0
1
0.0 0 .0 0 .0 0 .0 0 .0
0.0
0.08713
0.0 0 .0
0.00 0.0
0.0
0.0
0.0
1 0
1.0
1.0
1.0
1.0
1.0 1 .0
1 .0
1 .0 1 0
1.0
1 0
1.0 1 .0 1 .0
1 0
1.0
1.0
1.0
1.0 1.0 1.0
1 0
1.0 1.0 1.0 1.0 1.0 1.0
1 .0 1 .0
1.0
1 .0
0.000255
999.
The end ofthe input data for FARCON code.
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Page 25)
DISFAC Code (CNS Version)
INPUT
Description
Card No.
ormat Variable Description
- - ~ - - - - c - - c - - - - - - c - - -
1.
3 NCAS Number of problems to be run.
2.
20A4
TITLE(I)
Title of the problem.
3. 9F8.5
SIGAM
Macroscopic absorption cross section
for the moderator
cm -
1
SIGSM Macroscopic scatter ing cross section
for the moderator cm-
1
SIGAF Macroscopic absorption cross section
for
the
fuel
cm -
1
SIGSF Macroscopic scattering cross section
for the fuel
cm -
1
SIGFF Macroscopic fission cross section
for the fuel cm -
1
DIF
DifFusion
coefficient for the fuel cm-
1
DIM
Diffusion coefficient for moderator
cm-
1
A Radius of fuel cm)
X
Distance between centers adjacent fuel pins.
L
Geometry indicator, L = 1 for square lattice,
and L
=
2 for hexagonal lattice
a.
If
the NCAS
is
greater than 1, repeat the 2 and 3 cards for each problem.
c -
C DISFAC INPUT
D T for
Turkey Point Reactor [NASIR
M ]
.
C
This data can
be
generated
by
running DISGEN EXE
.
C Then store i t as
DISFAC DAT
f i le .
You
can
change
.
C the name or the data of th is
f i le
.
c
VAR1ABLE
INPUT
D T FOR DISFAC CODE [CNS] VERSION
Oct, 1994)
c
-
3
THIS IS A TEST
CASE FOR
DISFAC [NASIR M.], inner zone, turkey
point
.
. 02000 3.00880
.41332
.40013
.30159
.41207 .16124 .46600 1.50 1
THIS
IS A TEST
CASE FOR DISFAC [NASIR M.],
middle
zone,
turkey point .
. 02000 3.00880
.44519
.40037
.32895
.39684 .16124 .46600 1.50 1
THIS
IS A TEST
CASE FOR DISFAC
[NASIR
M.],
outer
zone,
turkey point .
. 02000 3.00880 .48725 .39646 .36563 .37912
.16124
.46600 1.50 1
The
end of data file for DISFAC.
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Modules: User s
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Page (26)
SLOWCON Code (CNS VERSION)
INPUT
Description
Card
No.
ormat
Variable
Description
1.
13 NCA5
r ~ u m r of problems to be run.
a
18A4
A(I)
Title of the problem.
3.
13
NINF r ~ u m r of Regions (at the most 5).
5F10.6
(RAD(I) 1=1,5)
Equivalent radius of each region
(in
increasing order of I (em), f I is greater
than NIN F than RAD(I)
=
0.0
12
ID Option. If ID - 1, atomic densities(N)
will be computed
by
the code.
If
ID
=
1, then N are input.
12 MICRO
Option. If it is set equal
to
zero, no micro
scopic cross section averge will be done.
If
it
is 1, than cross sections will
be
averaged over computed spectrum
4.
F16.8
BUCK
Total buckling for the first region
(cm-
Z
)
F16.8
T
Temperature (OK)
5 through
A4
1
N(l)
8 free spaces for element identification
A4 N(2)
12 M
Number of the element
b
F14.8
W
Atomic weight
F14.8 RO
Density (gm/cm
3
.
F14.8 ZI
Number of times an atom occurs
in
a molecule.
F14.8
VOL
Volume fraction for each element.
F16.8
D51TY
Atomic density
(at/barn-em) for
element
M,
ignore
if
ID is not equal to one.
22. F16.8 DE Energy increment
a:- The 4-22 cards must be repeated I\JINF time for each problem.
b
M Element
1 Hydrogen
5
Pu-240
9
U-236
13
5m-149
17
FP-U-235
The value of M for various elements
I
M Element M element
2
Oxygen
3
FP-Pu-239
6
U-238
7
Pu-242
10
Pu-239 11
Pu-242
14
Zr-2
15
55-304
M element
4
Carbon
8
U-235
12
Xe-135
ItB:J
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27)
c -
C SLOWCON INPUT DATA fo r Turkey
Point Reactor
[NASIR
M.]
.
C This da ta can be
generated
by running SLOGEN.EXE .
C Then s to re
t
as SLDWCON.DAT
f i l e .
You
can change
.
C
the name
or
the
data of t h i s
f i l e
.
c VARIABLE INPUT DATA FOR SLOWCON
CODE
[eNS] VERSION Oct,
1994)
c -
1
SLOWCON
CNS VERSION) [NASIR M.] 5 REGION
DATA FOR
TURKEY POINT
R.
5 88.104 124.020
151.76 169.545 173.990
1 1
.000255 293.
HYDROGEN
1
18. 1. 2. .59991
.04872
OXYGEN 2
18.
1.
1.
.59991
.038257
FP PU-39 3 110.
O. 1.
.0
.0
CARBON 4 12. O. 1.
.0
.0
PU-240 5 240.
O.
O. .0
.0
U-238
6 270. 10.9
1.0
.30243
.0067938
PU-242
7 242.
O.
O.
.0
.0
U-235 8
270.
10.9
1.0
.30243
.0001567
U-236
9 236. O. O.
.0
.0
PU-239 10
239.
O. O.
.0
.0
PU-241 11 241.
O. O.
.0
.0
XE-135 12
135.
SM-149 13 149. O. O.
.0
.0
ZR-2 14 90. 6.9
1.
.09766
.004122
SS-304
15 60. O. 1.0
.0 .0
B-l0 16 10.
O. 0.0
.0
.0
FP 1-35 17 110. O. O.
.0
.0
0.01
.000255 293.
HYDROGEN
1 18.
1.
2.
.59991
.0494
OXYGEN
2 18.
1. 1.
.59991
.038564
FP
PU-39
3
110.
O.
1.
.0 .0
CARBON
4 12.
O.
1.
.0
.0
PU-240 5 240. O.
O.
.0
.0
U-238
6 270.
10.9
1.0
.30243
.0067796
PU-242 7
242.
O.
O.
.0
.0
U-235
8 270.
10.9
1.0
.30243
.0001709
U-236
9 236.
O.
O.
.0
.0
PU-239 10 239.
O.
O.
.0
.0
PU-241
11 241.
O.
O.
.0
.0
XE-135
12 135.
SM-149
13 149.
O.
O.
.0
.0
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28)
ED
ZR-2
14
90.
6.9
1. .09766 .004157
8S-304
15 60.
O
1.0
.0 .0
B-l0
16 10. O
0.0
.0 .0
FP 1-35
17
110.
O
O
.0 .0
0.01
.000255 293.
HYDROGEN 1 18. 1. 2.
.59991 .05030
OXYGEN
2 18. 1.
1.
.59991
.03890
FP PU-39 3 110.
O 1.
.0 .0
CARBON
4
12.
O
1.
.0 .0
PU-240
5
240.
O
O
.0
.0
U-238
6
270.
10.9
1.0
.30243 .006687
PU-242 7
242.
O
O
.0
.0
U-235
8 270.
10.9 1.0
.30243
.0001899
U-236 9 236.
O
O
.0
.0
PU-239 10 239. O
O
.0 .0
PU-241 11
241.
O
O
.0
.0
XE-135 12 135.
8M-149
13
149.
O
O
.0
.0
ZR-2 14
90.
6.9 1.
.09766
.004202
8S-304 15 60. O
1.0
.0
.0
B-l0
16
10.
O
0.0
.0
.0
FP 1-35 17 110. O
O
.0
.0
0.01
.000255
293.
HYDROGEN
1 18. 1.
2. 1.
.0670
OXYGEN 2
18.
1. 1.
1.
.0335
FP PU-39 3
110.
O 1.
.0 .0
CARBON
4 12. O 1.
.0
.0
PU-240 5
240.
O O
.0
.0
U-238
6 270.
O
O .0
.0
PU-242 7
242. O
O
.0
.0
U-235
8
270.
O O
.0 .0
U-236
9
236. O O
.0
.0
PU-239 10
239. O
O
.0
.0
PU-241
11 241. O
O
.0
.0
XE-135
12 135.
8M-149 13
149. O
O
.0
.0
ZR-2 14 90.
O
O
.0
.0
88-304
15
60. O
O
.0
.0
B-l0
16
10.
O
O
.0
.0
FP 1-35 17
110.
O
O
.0
.0
0.01
Centre
or
Nuclear Studies
P.O.
Nilore
Islamabad
Pakistan.
-
8/10/2019 Pc Based Vpi Manual 1994
31/33
-
8/10/2019 Pc Based Vpi Manual 1994
32/33
PC-Based
VPI
Modules: User's Guide
Page (30)
ODMUG Code (CNS Version)
INPUT
Description
Card
No. ormat
Variable Description
1
12 BCl
Left boundry condition
[ = 1 for zero flux; = 2 for zero current]
12 BCR
Right boundry condition
[ = 1 for zero
fl
ux; = 2
for
zero
cu
rrent ]
F5.2 P
Geometry option, [ = 0 for slab,
=1 for
cylinder
and
2
for
sphere
12
NRGNS
Number of regions (upto maximmum 5).
F2.
JP
o
=
Poison
search, 1 = Poison search
EIO.3 EPS
Convergence parameter
on
eigenvalue.
13
G
Number of groups
2.
8F10.3 D EL(I),I=l, NRGNS) Width of region I (cm).
3.*
E9.3 ((DC(I,J),I=l,G), Diffusion coefficient of group I
J=l, NRGNS)
in
region
J
cm-
1
)
E9.3
((SA( I,J), 1=1,
G),
Macroscopic absorption cross section
J=l, f\ RG NS)
of group I in region J cm-
I
E9.3 ((5
R I
,J), 1=1,G),
Macroscopic
Removal
cross section
J=l, NRGNS)
of group I in
region
J
cm-
I
E9.3
((5 F I ,J), 1=1,
G),
Macroscopic Fission cross section
J=l,
f\IRGNS)
of group I
in
region
J
cm-
I
E9.3 ((5 P I ,J), 1=1,G),
Macroscopic absorption cross section
J=l, NRGNS)
for
Poisons of group I in region J cm-
I
E9.3
((5 NU I ,J), I=1,
G),
Value
of
for
J=l, f\
RGNS)
grou p lin region J
E9.3
((BU
K I ,J),I=l,G),
Transverse buckling
J=l,
NRGNS)
of group I in
region
J cm-
2
3+G
*
E10.5 POWER Desired power level (Watts)
NRGNS
E10.5
PHIB Ratio of average to peak
flux
in
transverse direction R
y
-R
z
for a slab,
R
z
for
cylinder,
and
1
for
sphere).
E10.5
HT
Product of height
and
depth for a slab,
height for cylinder, 1.0 for sphere.
3+G *
F10.5 DESEIG
Desired value of
f
NRGNS+1
for poison
search
(ignore FlO.5
FPS2
Convergence criterion for poison
if
JP
= 0)
search (recommended
10
times EPS)
* There are
G*I\J
RNS cards of type 3.
Centre for Nuclear Studies, P.o. Nilore, Islamabad,
Pakistan.
-
8/10/2019 Pc Based Vpi Manual 1994
33/33
PC-Based VPI
Modules: User s Guide
Page
(31)
c
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
C O MUG INPUT DATA for Turkey
Point
Reactor [NASIR
M J
C This data
can
be generated by running
ODGEN EXE
C Then s tore i t as
ODMUG DAT
f i l e . You can change
C the name or the data of
th i s
f i l e .
The
data is based on
C outputs
from FARCON and SLOWCON
for 5 regions of Turkey Point
C Reactor at
cold condit ion
(T=293 degrees F).
c VARIABLE INPUT DATA FOR
O MUG CODE [CNS]
VERSION Oct, 1994)
c
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
2 1
1.
5 0
1.
E-04 3
88.104
35.916
27.745 17.780
4.445
1.425
2.642E-035.563E-023.034E-030.0
2.62
5.595E-05
LO.668
1.677E-028.294E-027.868E-030.
2.43
5.595E-05
0.2052 9.939E-020.0 1.524E-010.0
2.43
5.595E-05
1.426 2.666E-035.561E-023.090E-030.
2.62
5.595E-05
0.667 1.719E-028.269E-028.576E-030.0 2.43
5.595E-05
0.2029 1.059E-Ol0.0 1.657E-010.
2.43
5.595E-05
1.432
2.674E-035.554E-028.140E-030.0 2.62
5.595E-05
0.668 1.775E-028.236E-029.521E-030.
2.43
5.595E-05
0.1997 1.146E-010.0 1.835E-010.0
2.43
5.595E-05
11.582
O 8.629E-020.0 O
O
5.595E-05
lO.576
O
1.525E-010.0
0.0
O
5.595E-05
0.1687 1.627E-020.0 0.0
0.0 0.0
5.595E-05
1.543 1.210E-031.363E-030.0
0.0
0.0
5.595E-05
0.375 9.216E-031.186E-040.0 0.0
0.0
5.595E-05
0.3456 7.228E-020.0 0.0
O
0.0
5.595E-05
2.09700E+90.75 365.76
The end of
the
input data for ODM UG code.
With tris we reach
at
the end of user s guide.
All thes
sample results can be seen in
the director after
you
have copied the
file vpi
from
the
diskette and exploded
it in the
main
directory. The result files are labelled as *.RES.