Pc Based Vpi Manual 1994

8/10/2019 Pc Based Vpi Manual 1994

1/33

PC Based VPI odules:

User's Guide

1tMbt1lt

Centre

or

Nuclear

Studies

P o Nilore, Islamabad

Pakistan

October, 1994


2/33

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.


3/33


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.

Centre for Nuclear Studies, P.O. Nilore, Islamabad, Pakistan.


4/33

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.

Centre

for

Nuclear

Studies,

P.O.

Nilore, Islamabad,

Pakistan.


5/33


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.

Centre

for

Nuclear Studies,

P.O.

Nilore,

Islamabad, Pakistan.


6/33


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.

Centre

for Nuclear

Studies, P o Nilore,



7/33


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

Centre for

Nuclear

Studies,

P.O. Nilore, Islamabad, Pakistan.


8/33


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

Centre for

Nuclear

Studies, P.O. Nilore,

Islamabad,

Pakistan.


9/33

PC-Based

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,

~

CentI e

for

N udear Studies,

P.O.

Nilore, Islamabad,

Pakistan.


10/33

pc-

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.

Centre

for

Nuclear

Studies, P.O. Nilore, Islamabad,

Pakistan.


11/33

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


Hot

Leg

Coolant

Outlet

====

Cold

Leg

Collant Inlet

Fig 1 Pressure Vessel

and

Coolant Flow for a Typical

PWR

Centre

for

N

udear

Studies, P.O. Nilore, Islamabad,

Pakistan.


12/33

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

Centre for

Nuclear

Studies, P.O.

Nilore,

Islamabad,

Pakistan.


13/33


Page

11)

-

Fuel Rod

Water Hole

igo 3 Fuel

Assembly Cross Section

Centre for Nuclear Studies,

P.O. Nilore,



14/33

PC-Based

VPI


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

Centre

for Nuclear Studies,

P o

Nilore, Islamabad,

Pakistan.


15/33

PC-Based

VPI


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

Centre

for

N

uc1ear

Studies, P G

Nilore,

Islamabad, P:t kistan,


16/33

PC-Based VPI rvlodules:

User s

Guide

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.


17/33


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.


19/33


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.


20/33


21/33


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



22/33

PC-Based

VPI


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.


23/33

PC-Based

VPI


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

Centre

for

Nuclear

Studies,

P.O. Nilore, Islamabad, Pakistan.


24/33


Page 22)

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

Centre for Nuclear

Studies,

P.O. Nilore,

Islamabad,

Pakistan.


25/33

PC-Based

VPI Modules: User's Guide

Page (23)

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

Centre

for

Nuclear Studies, P.O.

Nilore,

Islamabad,

Pakistan.


26/33

PC-Based VPI Modules: User'sGuide

Page

(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.

Centre

for


Nilore,



27/33

PC-Ba.sed VPI Modules: User's Guide

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.

Centre for


Nilore,



28/33

PC-Based VPI

Modules: User s

Guide

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

Centre for

Nuclear

Studies, P.O.

Nilore, Islamabad, Pakistan.


29/33

PC-Based

VPI Modules: User s Guide

Page

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

Centre

for



30/33


Page

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

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Nuclear Studies

P.O.

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Pakistan.


31/33


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),


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),


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.


33/33

PC-Based VPI


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.

Documents

Pc Based Vpi Manual 1994