NUREG/IA-0005

Al• kIntemlational

Agreement Report

Assessment of RELAP5/MOD 2,

Cycle 36, Against FIX-Il Split Break

Experiment No. 3027

Prepared by

J. Eriksson

Swedish Nuclear Power Inspectorate

P.O. Box 27106

S102 #52 Stockholm, Sweden

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, D.C. 20555

September 1986

Prepared as part of

The Agreement on Research Participation and Technical Exchange

under the International Thermal-Hydraulic Code Assessment

and Application Program (ICAP)

Published -by

U.S. Nuclear Regulatory Commission
NOTICE

This report was prepared under an international cooperative

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the United States Government nor any agency thereof, or any of

their employees, makes any warranty, expressed or implied, or

assumes any legal liability or responsibility for any third party's

use, or the results of such use, of any information, apparatus product or process disclosed in this report, or represents that its use

by such third party would not infringe privately owned rights.

Available from

Superintendent of Documents

U.S. Government Printing Office

P.O. Box 37082

Washington, D.C. 20013-7082

and

National Technical Information Service

Springfield, VA 22161
NUREG/IA-0005

Intemational

Agreement Report

Assessment of RELAP5/MOD 2,

Cycle 36, Against FIX-Il Split Break

Experiment No. 3027

Prepared by

J. Eriksson

Swedish Nuclear Power Inspectorate

P.O. Box 27106

S102 #52 Stockholm, Sweden

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, D.C. 20555

September 1986

Prepared as part of

The Agreement on Research Participation and Technical Exchange

under the International Thermal. Hydraulic Code Assessment

and Application Program (ICAP)

Published by

U.S. Nuclear Regulatory Commission
NOTICE

This report documents work performed under the sponsorship of the SKI/STUDSVIK

of Sweden. The information in this report has been provided to the USNRC

under the terms of an information exchange agreement between the United States

and Sweden (Technical Exchange and Cooperation Arrangement Between the United

States Nuclear Regulatory Commission and the Swedish Nuclear Power

Inspectorate and Studsvik Enerigiteknik AB of Sweden in the field of reactor

safety research and development, February 1985). Sweden has consented to the

publication of this report as a USNRC document in order that it may receive

the widest possible circulation among the reactor safety community. Neither

the United States Government nor Sweden or any agency thereof, or any of their

employees, makes any warranty, expressed or implied, or assumes any legal

liability of responsibility for any third party's use, or the results of such

use, or any information, apparatus, product or process disclosed in this

report, or represents that its use by such third party would not infringe

privately owned rights.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 iii

1985-10-22

SKI Project 85026, 13.3-917/84

John Eriksson Swedish Nuclear Power Inspectorate

I CAP

Assessment of RELAP5/MOD2, Cycle 36, Against

FIX-II Split Break Experiment No 3027

ABSTRACT

The FIX-II split break experiment No. 3027 has

been analyzed using the RELAP5/Mod2 code. The code

version used, Cycle 36, is a frozen version of the

code.

Four different prediction calculations were

carried out to study the sensitivity on various

parameters to changes of break discharge, initial

coolant mass, and passive heat structures. The

differences between the calculations and the

experiment have been quantified over intervals

in real time for a number of variables available

from the measurements during the experiment.

The core inventory expressed by the differential

pressure over the core was generally underpredicted.

Dryout times were generally overpredicted, probably

due to differences in the used dryout correlation.

App rove&.

STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 v

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LIST OF CONTENTS

Page

1. INTRODUCTION 1

2. FACILITY AND TEST DESCRIPTION 3

2.1 Test facility 3

2.2 The experiment 5

2.3 Measurement uncertainty 7

3. CODE AND MODEL DESCRIPTION 9

3.1 The code features 9

3.2 The calculation input model 10

4. THE BASE CASE CALCULATION 12

4.1 Base case calculation results 12

5. SENSITIVITY RESULTS AND DISCUSSION 17

6. RUN STATISTICS 20

7. CONCLUSIONS 21

REFERENCES 23

FIGURES 24

TABLES 31

APPENDICES

A. Input listings

B. Data comparison plots

C. Calculation to experiment data uncertainties

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1. INTRODUCTION

There is a growing interest in modifying existing

rules for reactor licensing and safety thermalhydraulic calculation away from those stated in

Appendix K (1) towards procedures based on best

estimate types of calculations. Although Appendix K furnishes a set of skillfully and simply

phrased rules, its present and inherent conservatism on safety has been partly regarded as in

growing contradiction to the increasing knowledge

gained from experimental programs. The many

advanced best estimate thermal-hydraulic reactor

codes in existence today demonstrate this.

When the simply formulated older calculation rules

were replaced by best estimate type calculation

procedures another measure of reliability had to

be found to replace the earlier conservatism. To

intentionally fulfill that aspect of a code the

natural course will be an assurance of a reasonable reliability of the predicted data. Plans for

conducting code assessments for the purpose of

deteirmining the accuracy and the validity of

advanced LWR system codes were proposed some

years ago (2). Today the International Code

Assessment Program (ICAP) is in progress, under

the auspices of the USNRC (3).

The calculations presented in this report is a

Swedish contribution to the ICAP. The contribution

is funded by the Swedish Nuclear Power Inspectorate.

In the present study the frozen version of RELAP5/

MOD2 is assessed against LOCA experiment No. 3027,

carried out the FIX-II test facility at Studsvik.

The experiment is one of a test series, see Table 1,

conducted in 1984. This test was conducted to check

the reproducibility of Test 3025, which had been
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used as a "double-blind" international standard

problem (ISP-15).

A description of the test facility and this particular test is provided in Chapter 2. A description of the input model is given in Chapter 3.

The base case and sensitivity calculations are

discussed in Chapters 4 and 5. Run statistics

are given in Chapter 6. General conclusions are

drawn in Chapter 7.

Appendix A contains the complete input lists.

The data comparison plots are inclided in

Appendix B. Finally, results of the statistical

analyses of differences between experiment and

predictions for discrete time intervals are

included in Appendix C.
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2. FACILITY AND TEST DESCRIPTION

The FIX-II integral test facility was completed

at the end of 1981. It is run by Studsvik Energiteknik AB under contract to the Swedish Nuclear

Power Inspectorate. The experimental program

comprises investigations of the fuel-to-coolant

heat transfer. Various blow-down and pump trip

situations conceivable in Swedish BWR's are

simulated.

2.1 Test facility

The test facility itself, which is assumed to be

stripped from gear not involved in the present

experiment, is shown in Figure 1. The volume

scaling is 1:777 of the Oskarshamn-II reactor,

which is of the ASEA-ATOM external recirculation

pump design. An exhaustive description of the

FIX-II test facility may be obtained from Ref 4,

which also provides additional references where

various problems pertaining to the construction

period are discussed. Therefore, only some

fundamental aspects of the facility will be

presented here.

The core model involves a full length rod bundle,

which in the geometry is closely related to a

fuel element of the ASEA-ATOM design and electrically heated by DC. Here, however, there are

only 6 x 6 rod simulators instead of the 8 x 8

rods in a fuel element. Figures 2 and 3a show

details from the core simulator design. As seen,

filler bodies are placed between the square-section

fuel channel and the circular-section pressure

vessel to reduce the water-filled volume, which

otherwise may influence the test by the leakage

of steam to the upper plenum. The water surrounding

the fillers is externally recirculated and cooled

by 200 to 250 kW.
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1985-10-22

The upper part of the pressure vessel, Figure 3b,

holds the steam separator and the steam condenser

volume with its three sprinklers. During steady

state power operation the steam outlet is closed.

The turbine power is modelled by the partial

circulation of water from the downcomer through

an external 6 MW cooler with feedback to the

sprinklers of the steam condenser and into the

upper part of the downcomer. The flow rate in

the two branches with cooled water is adjusted

to control the pressure and the inlet subcooling.

The remaining downcomer flow, representing the

recirculation coolant flow in the reference

reactor, splits at the lower downcomer end into

two loops. One loop represents three of the intact recirculation lines of the reference reactor,

while the other loop, representing a fourth recirculation line, incorporates the break devices.

Both loops have a recirculation pump. The intact

loop pump speed is regulated according to a predetermined speed history.

The FIX-II has, as part of the core model, an

external bypass simulator through which about

12 % of the recirculation mass flow branches out

through a regulation valve. This bypass is

heated separately to represent the channel wall

heat transfer. At the lower end of the bypass,

Figure 3c, there is a stagnant water volume to

simulate the reference reactor area for the

control rod guide tubes.

Since the FIX-II facility has been designed for

blowdown experiments only, no emergency core

cooling equipment is installed.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 5

1985-10-22

The data collection system is constructed around

a signal processor controlling 192 measurement

channels. The selection of measurements is made

in a signal exchange terminal. A multipurpose

minicomputer transfers the raw-data of measured

parameters to a magnetic tape. From this tape,

the final analysis at the central computer gives

the desired tables and plots from an experiment.

The data acquisition system includes measurements

to obtain:

- pressures (PT)

- differential pressures (dPT)

- temperatures of fluids (TE)

- mass flow (dPT, PT, TE)

- electric currents (I) and voltages (U)

- pump speeds (nT)

- water level positions (CE)

- valve positions

at places shown in the instrumentation diagram,

Figure 4.

For recording clad temperatures there were about

100 thermocouples engaged at 16 axial levels of

the heated length in the 36-rod bundle.

2.2 The experiment

The preparation of the experiment is initiated

several hours before the actual experiment. For

the heat-up of the facility, a 200 kW preheater

is involved for a period lasting about 5 h. The

recirculation pumps are running during this period

too. Initial conditions are then established by

switching the power supplies to the bundle and
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 6

1985-10-22

the bypass with the 6 MW cooler and the condenser

spray in operation. The preheater is now disconnected. For about 10 to 30 minutes, the

electric power to the rod bundle and the bypass

heating is gradually increased until the initial

test conditions are reached. Necessary calibrations are made, and once the equilibrium conditions

are finally approved, the sequency control

equipment is activated for break opening, valve

manoeuvres, power reduction, pump speed changes

and so forth, according to a programmed scheme

for the test. For the split break test No. 3027,

the transient ends 85 s after opening of the

break.

In the present FIX-II experiment, the speed of

the pump on the intact recirculation line decreased from the break time to about 20 % of the

initial speed at end of the transient. The speed

of the broken recirculation line pump was not

adjusted.

The break flow escaping through the fast opening

break valve, Figure 1, is discharged into the

receiving tank, T2. Initially, the tank is

partly filled with cold water for efficient pool

condensation of the break flow.

The split break assembly consists of a T-piece

on the line from pump P2 to the lower plenum. A

break flow limiting orifice, downstream of the

break isolation valve, consists of an exchangeable conical inlet part followed by a restriction

pipe. In experiment No. 3027, the restriction pipe

and flange diameter was 12 mm corresponding to a

31 %. area of one recirculation line.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 7

1985-10-22

Apart from the heat removal from the filler body

space, see Chapter 2.1, some 100 kW are also

lost by the non-perfect insulation encapsulating

the recirculation lines and the pressure vessel.

The magnitude of the steady state heat losses

was one argument for not performing experiments

with very small break areas at FIX-II. For BWR

plants, the break size used is more interesting

than small leakages.

The main measured parameters for the steady

state before break are reproduced from Ref 3 in

Table 4. The test performance chronology, related

to the programming of the sequence control equipment, is given in Table 5.

Experimental raw data were collected for the

whole period of the transient. However, internal

flows were then only evaluated until about 30 s

due to uncertainties expected with the two-phase

flow rate measurements.

A summary of the main results (including event

times, maximum cladding temperatures and some

peak mass flows) is given in Table 6, see also

Ref 5.

2.3 Measurement uncertainty

To obtain estimates for the accuracy of the measured data, test procedures were adapted within

the experimental program. Probable errors and

errors corresponding to a 95 % confidence level

as derived from these tests are summarized in

Table 2a. The probable errors of derived quantities, foremost mass flows, are given in Table 2b.

The pump speeds are measured and controlled using a
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 8

1985-10-22

tachometer of a 1 r/s accuracy. The pump characteristics, on the other hand, were verified against

the manufacturer's data for cold water single

phase operation, however, no tests of an in-loop

hot water performance were conducted (private

comm L Nilsson).
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3. CODE AND MODEL DESCRIPTIONS

The assessment calculation for the FIX-II experiment No. 3027 was done using the RELAP5/Mod 2,

Cycle 36, code received at the beginning of

February 1985. The descriptive document available

for this code at the time of preparing the calculation input was the rather detailed code manual

(7) also explicitly containing an input data requirements manual. The code features are discussed

in Chapter 3.1.

Due to the close relation to the RELAP5/Modl

code, which has been extensively used at STUDSVIK,

an existing input for the FIX-II test No. 3025

(6, 8), the previous ISP-15 exercise, formed the

basis for the present RELAP5/Mod2 input. Details

of the input are discussed in Chapter 3.2. Here

the steady state calculation is assumed to be

part of the input preparation.

3.1 The Code Features

An extensive code description for the RELAP5/Mod2

is given in the Ref 7. The main characteristics of

the code are summarized in Table 3.

Since the RELAP5/Mod2 code is primarily developed

for pressure reactor application, the question

arises whether some important features are

missing from the code for a BWR-type application

like the present FIX-II experiment. A key peculiarity in this respect, is the absence in the

FIX-II facility of a core top spray cooling

due to the fact that facility is designed for

experiments until end of blow-down only. The

steady state cooling, however, is accomplished

by a cold water injection at the top of an
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internal condenser space above the core and the

steam separator. The condenser space is voluminous;

it results in about three quarters of the total

system space being above the core top level.

Thus, it is assumed that the condenser spray

vaporizes without impact on the core behaviour

during normal operation. Deficient sophistication

in modelling droplet flows in RELAP5/Mod2 should,

therefore, be far less important when predicting

the present experiment than in the case of an

experiment also including core cooling by refill

and core top spray.

3.2 The calculation Input Model

The model geometry used in the present calculations is closely related to geometries used in

several previous calculations for FIX-II experiments using previous RELAP5/Modl code versions

(6 and 8). The nodalization diagram for the

geometric modelling used is shown in Figure 5.

Figures 6 and 7 account for the modelling in the

geometry of the test facility.

To reproduce fundamental measured steady state

quantities, see-Table 4, the input for the

steady state search run was modified by some

additional components and regulating control

systems:

I To obtain the steady state dome pressure,

a time dependent volume outside of the

opened steam relief valve was added. This

volume had the experimentally measured

dome pressure rather than the atmospheric

outside pressure later during the transient.

II The speed of the pumps P1 and P2 was regulated using the RELAP5 control system

to fulfill the measured mass flows.
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III To branch off the correct mass flow

into the core bypass, the junction from

the lower plenum was modelled as a

motor valve. By trip logic, the opening

of that valve was regulated to give

the experimental bypass mass flow. When

entering into the transient calculation,

the valve setting was logically latched.

IV The measured steam separator collapsed

level was satisfied by connecting an

auxiliary time dependent volume to the

top of the steam separator. The connecting junction was modelled to regulate

the collapsed level by water phase flow

rate, depending on the level height error.

V The calculation was performed using the

RELAP5/Mod2 steady-state option.

Evidently, some non-zero flows (points I and IV)

will remain in the junctions from the pressureand level regulating time dependent volumes.

These flows are quite small and are influenced

by the system heat balance.

The input for the steady state calculation is

given in the Appendix A.
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4. THE BASE CASE CALCULATION

The transient calculation of the base case

(called Case A) was based on the restart-plot

file obtained from the previously discussed

steady state calculation. The additional components and regulators discussed in Chapter 3.2

were deleted, see the transient restart input in

Appendix A.10. The calculation was performed

under the transient calculation option. In addition, when verifying the quality of the steady

state, the opening of the break was delayed.

The calculation of the transient itself was

carried out without any particular problems.

The smooth lapse of the CPU-time, Plot B.34 and

of the computation mass error, Plot B.35, again

indicate this.

4.1 Base case calculation results

A set of results from the base case calculation

and the sensitivity calculations were selected

to fulfil the requirement on assessment parameters given in Table 3 of Ref 3. Those parameters

plotted are listed in the Table 8 and the corresponding plots reproduced in Appendix B. Since

some of the parameters are not available from the

experimental measurements, only the comparisons

between the different calculations are shown in

the plots, compare Table 8. As regards the mass

flow comparisons, it must again be pointed out

that the experimental data are not reliable after

voiding has begun which for most measurement

positions occurs about 20 s after the break

time.
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The system boundary conditions concerning the

total mass inventory are the shutting of the

spray flow and the feed water valves, which take

place very soon after the break occurs. There is

a good correlation between calculation and

experiment in the mass flow rate through the

steam relief valve, plot B.27. However, the

break mass flow which in the experiment is

measured by the increasing content of a flow

receiving tank, plot B.30, has been obviously

underestimated in the base case calculation.

Plot B.29, where the experimental curve is

derived from the receiving tank content, shows

the same break flow underestimation from the

calculation, particularly up to 30 s. Plot B.29

shows a pronounced peak in the measured mass

flow during the very first seconds after the

break on account of steam accumulating in the

tubes leading from the break to the condenser

receiving tank, where previously only water was

present. This results in a measured superimposed

volume equivalent to a water mass of about 20 kg

from about 3 s from the end of the test. At the

end of the test, the break valve is closed

causing the receiving tank mass content to

reduce with the superimposed steam volume, see

Plot B.30. In the light of this correction to

the total experimental break loss, the base case

calculation underestimated the break loss by

about 30 kg until end of the test. The calculated

mass inventory in the system, Plot B.26, obviously

has the opposite time elapse to that of the

integrated break loss.

The thermal-hydraulic conditions in the system

are also partly controlled by heat exchange with

the core and other'boundary structures. Plot B.3

shows the calculated heat exchange with all the
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passive wall structures in the loop except for

the separate filler body space with a known

cooling power of about 260 kW in steady state

operation. As Plot B.3 shows, the heat returning

from the passives does exceed the decay core

heating from about 30 s on. Thereby, the structure

wall thickness was generally selected at 0.09

times the tube inner diameter, also compensating

for flanges and other extras.

System pressures, Plots B.20, B.21 and B.33 were

well predicted over the whole transient for the

base case. The cycling of the steam relief valve,

compare Plot B.27, dominates the behaviour of the

system pressure.

From the experiment, evaluated in-loop main recirculation flows are available at the bypass

inlet, at the pressure sides of the two main

pumps and also at the broken loop between break

and vessel inlet, see Plots B.22, B.23, B.24 and

B.25. Two additional measurements valid for inloop mass flows are the differential pressures

over the orifice in the steam separator, Plot B.17,

and over the core inlet restriction, Plot B.2. As

mentioned before, the mass flows evaluated from the

experiment, i.e. plots B.22 through B.25, are not

reliable after the formation of steam has started.

On the plots, the time for initiating steam formation is clearly seen to range between 20 and 25 s

as enhancing flow oscillations. Up to that time,

the predicted base case flow rates essentially

compare well with the measurements. The most

conspicuous differences are that the mass flows

at the broken loop pump and at the broken loop

vessel inlet, plots B.24 and B.25, are underestimated in their magnitude thus showing an

underestimation in the break flow.
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1985-10-22

Plots B.1, B.13 and B.28 show calculated fluid

densities at the core bottom, at the reactor

vessel bottom and upstream of the break. Fluid

densities were not directly measured in the

experiment.

Several fluid temperature measurements were

carried out in the experiment. At the break,

plot B.31, there is a good agreement between the

base case calculation and the experiment, similarly also after about 15 s at the downcomer

bottom, Plot B.19. The difference in the calculated and-the experimental fluid temperatures at

the downcomer bottom before 15 s is due to the

amount of void. In the experiment, the measured

two-phase level did not reach the downcomer

bottom until about 13 s (5), see also Plot B.14.

The temperatures at the core inlet, Plot B.10,

at the core outlet, Plot B.11, and in the upper

plenum, Plot B.18, all show underestimations in

the calculation after some 50 s, although the

system pressure compares well with the experiment.

The calculated temperature is still typically

that of saturation at the high void while in the

experiment, slightly superheated pure steam

fills the vessel.

The fluid inventories of the core, Plot B.12,

the upper plenum, Plot B.16, the downcomer,

Plot B.14, and of the lower plenum, Plot B.15,

are compared in the quantity of differential

pressures as directly measured in the experiment.

The differential pressure over the core, Plot B.12,

is underpredicted during the period between 2.3

and 12 s when the steam relief valve is closed.

In the calculation, the main part of this differential pressure is due to the dynamic two-phase

wall friction. As the core boundary mass flows
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1985-10-22

compare reasonably well in the time interval,

the difference in the core differential pressure

is most likely caused by a strong wall friction

dependance on the void fraction profile in the

core. The differential pressure in the lower

plenum, Plot B.15, is overpredicted in the base

case after about 30 s. Comparison with Plot B.13

shows the dependance of the differential pressure

on the fluid density at the bottom of the vessel.

The comparisons of the rod clad temperatures are

done at the clad inner surface which is most

closely equivalent to the thermocouple positions

of the heated rods in the experiment. The rod

calculated clad temperatures, Plots B.4 through

B.9, agree reasonably well at various levels of

the core with the measurements in the experiment

until dryout conditions occur. Above the core

midplane, levels 9, 12 and 15, the dryouts are

predicted to occur definitely later than in the

experiment. Actually, the calculated dryout of

all levels was delayed until the void was .985

or higher. In RELAP5/Mod2 the critical heat flux

is calculated according to a modified Zuber

correlation using l.-a (a is the steam void) as

a factor. This should be compared with the

corresponding RELAP5/ Modl correlation using

.96-a as a factor in the critical heat flux

expression, also in a modified Zuber correlation.

The delay in the outset of the calculated dryouts

is probably a result of the critical heat flux

correlation rather than of errors in the core

voids.
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1985-10-22

5. SNESITIVITY RESULTS AND DISCUSSION

The base case calculation (Case A) compared well

with the experiment on many parameters, however,

in the important heater rod temperatures after

dryout, a better prediction was desired. Consequently, with the aim of lowering the core

void, the break discharge coefficient, having

been .85 in the base case, was assumed to be

1.0 in a first sensitivity calculation, Case B.

Actually, Plots B.5 through B.8 show a better

agreement in the clad temperatures at the high

power levels of the model rod. At the low power

levels at the bottom and at the top of the core

the comparison was no better. Looking at hydraulic

quantities the differential pressure over the

core, Plot B.12, the system pressure, Plot B.20,

and the reversed broken loop cold leg flow at the

vessel inlet, Plot B.25, changed for the worse.

However, the most striking evidence that the increase of the break mass flow had been constructive was the far better agreement in the

mass loss, Plot B.30.

A source of uncertainty regarding the experiment

is the amount of initial fluid in the facility

before the break. The water volume in the experiment was accounted for by the water level in the

downcomer part of the steam condenser (5). In

the steady state calculation, that same level had

been satisfied using a regulating system for an

auxilliary flow between the loop and a time dependent volume containing saturated water. Examination

of data from other FIX-II tests indicated that the

initial mass of about 285 Kg, obtained by leveling

off the downcomer water level according to measurement, might be a lower limit of the mass in the
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1985-10-22

system. Differences-between the initial masses

in the calculation and in the experiment arise

from water in the spray, the feedwater, the

cooling return lines and some additional short

blind lines ending in valves which are closed in

the experiment. The mass of water in those lines

is estimated at about 4 kg. Another potential

source of initial mass difference is the amount

of liquid in droplet form in the steam condenser.

Since the volume of the condenser is about.6 m 3 ,

an actual void fraction of - .90 in the experiment

instead of - .96 in the calculation means a mass

difference of about 26 kg. Actually, the calculated droplet - water falling velocity of

1.2 M/s in the steady state is too high. According

to the spray nozzle manufacturers specification,

the spray mean droplet diameter at the actual

water flow should be about .9 mm or some 1.0 mm

after steam condensation. With this droplet

size, the droplet falling velocity is only about

.8 m/s relative to the upward velocity of steam

of .2. m/s. The conclusion must be drawn that the

calculation greatly underestimates the condenser

water mass estimates. In a second sensitivity

calculation, Case C, again with a discharge

coefficient of 1.0, the calculating was done

using an initial mass of 315 kg instead of

285 kg. Plot B.30 now shows a good agreement

between the predicted break mass loss and the

final experimental mass accumulated in the break

receiver after closing the break. Fluid temperatures, Plots B.10, B.11, B.18, B.19 and B.31,

which had worsened by the sole increase in the

discharge coefficient in Case B, again agreed

with the experiment in the Case C run. As a

consequence, the same statement also applies to

the system pressures, Plots B.20, B.21 and B.33.
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1985-10-22

On the other hand, the pressure drops in the

downcomer and in the lower plenum, Plots B.14

and B.15, do indicate same overestimatation in

the system fluid mass. The prediction of the

heated rod clad temperatures remained the same

as in the base case and the Case B calculation.

The amount heat returning from the passive

structures, Plot B.3, is essential during the

later part of the transient. Though the structure

wall thicknesses were chosen by a simple rule of

thumb, the structure modelling is believed to be

reasonably reliable. To quantify the effect of

the structure heat exchange on the system, a

calculation, case D, was performed using the

larger discharge coefficient and the larger

initial mass but removing all passives. Fluid

temperatures such as at the core inlet, Plot B.10,

naturally decreased more rapidly towards the end

of the transient. An interesting discovery is the

close simliarity in the system pressure between

calculation Case B and Case D. This similarity

may be explained in terms of the system that is,

if it is due to the heat structures or if it is

due to an amount coolant that has been added

itself. From about 30 s until the end of the

transient, the heat returning from the structures was about 12 MWs, see Plot B.3. In the

Case B calculation, Plot B.26 shows a decrease

at the same time, of the calculated mass content

from 110.5 to 35.2 kg. In case D, the decrease

is from 132.5 to 50.75 kg.. Reading the system

pressures of 4.7 MPa at 30 s and 1.9 MPa at 75 s

from Plot B.20 and using approximate changes in

the enthalphy obtained from the water data,

Case B shows about 11 MWs less enthalpy increase

than Case D due to differences in mass content.

This is close to the 12 MWs missing with the heat

structures absent in the Case D calculation.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 20

1985-10-22

6. RUN STATISTICS

The transient calculation model used with the

base case RELAP5/Mod2 prediction for the FIX-II

test No. 3027 was modelled by:

58 volumes

60 junctions

70 heat structures

The volumes number includes two pump components

and five time dependent volumes and among the

junctions there are two valve components and

four time dependent junctions.

The computer efficiency is summarized in Table 7

from the Major Edit print outs, see also Plot

B.34. The table also gives the number of time

step reductions from requested time steps forced

by the current transport limit in the interval

from the previous Major Edit. Actually the requested maximum time steps, as input values, were

set high, thereby forcing the code to establish

its own time steps.

The transient calculation needs were:

computer time CPU = 828.3-118.1=710.2 s

number of time steps DT = 972-200=782

number of volumes C = 58

transient real time RT = 75. s

from which also a code efficiency factor of

CPU x 103 = 15.7

C x DT

is obtained, compare Ref 3. The computer used

was a Cyber 180-835.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 21

1985-10-22

7. CONCLUSIONS

The calculation for the FIX-II No. 3027 split

break and a calculation for the LOBI ISP-18 test

carried out at the same time, were the first

assessments done at Studsvik using the RELAP5/Mod2

code. As a lot of experience on preceeding RELAP

codes had already been gained there were no

particular problems in getting along with the

RELAP5/Mod2. The difficulty with problems in a

calculation like this, lies in making sure that

the specifications for the two thousand lines of

input are as correct as possible.

Although the results may seem to be credable from

the calculations, there are some parameters which

do cast doubt on the prediction quality. A key

parameter among these being the pressure difference

over the core which was underestimated. This example

also emphasizes the problem of reading the information of coolant mass distribution in the experiment.

In the experiment there were no in-system void

measurements and the orifice mass flow measurements

were also unreliable after flashing had begun. The

cause of the lack of agreement in the core head

therefore remains undetermined.

Important differences between experimental and

calculated dryout times at various elevations

were noted. This could have beed caused by

inability to predict the core inventory or by

an inadequate dryout correlation. It is noted

that dryout was calculated only for very high

void fractions. It might therefore be suspected

that the discrepancies are mainly caused by the

dryout correlation.

In the present calculation, the RELAP5/Mod2 code

was not faced with a core top spray. However,
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 22

1985-10-22

the condenser in-loop spray cooling caused trouble

because the code is only capable of describing the

condenser hydraulics by using the vertical slug

flow regime available. Because of this the water

content in the condenser was underestimated by a

factor of about two.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 23

1985-10-22

REFERENCES

1. Acceptance Criteria for Emergency Core

Cooling Systems for Light-Water Cooled

Nuclear Power Reactors, 10 CFR, Part 50

(Appendix K), Fed Regist, 39(3).

(January 1974).

2. FABIC S and ANDERSEN P S

Plans for Assessment of Best Estimate -.LWR System Codes.

U.S. Nuclear Regulatory Commission

NUREG-0676.

3. ODAR, F and BESSETTE D E

Guidelines and Procedures for the

International Thermal-Hydraulic Code

Assessment and Applications Program

(Draft).

U.S. Nuclear Regulatory Commission, 1985.

4. NILSSON, L and GUSTAFSSON, P-A

FIX-II LOCA Blowdown and Pump Trip Heat

Transfer Experiments, Summary report

for phase 2: Description of experimental

equipment.

STUDSVIK/NR-83/238, Parts 1, 2 and 3.

5. NILSSON, L et al

FIX-II - LOCA Blowdown and Pump Trip

Heat Transfer Experiments. Experimental

results from LOCA test No. 3027.

STUDSVIK/NR-84/485.

6. ROSDAHL, 6 and TANGEN, K

Numerical simulation of the FIX-II test

3025 (ISP-15) split-break LOCA using

RELAP5/MOD 1. Post-test analysis

STUDSVIK/NR-83/330.

7. RANSOM, V H and WAGNER, R J

RELAP5/MOD 2 Code Manual

Volume 1: Code Structure Systems Models

and Solution Methods.

Volume 2: Users Guide and Input Requirements.

EGG-SAAM-6377, EG & G Idaho, Inc.

April 1984.

8. ERIKSSON, J

Analysis of the FIX-II Split-Break

Experiment (No 3031) using the RELAP5

code.

STUDSVIK/NR-84/396.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99

1985-10-22

24

Steam condensor

with steam separator

, -'!ýVý I,-; zylýu

Figure 1

View of the FIX-II facility, condition for split

break experiments.
Outlet end

Heated length

U)

'-4

C)

'-4

H

part

'00

0

to3

U)

'1-1

Inlet end

1 101.8 .

Figure 2.A Figure 2.B

Cross section of pressure vessel Design of a fuel rod simulator

and rod bundle

N) Ln
Spray

inlets

Bypass

corm, t

Rod bundle

Bypass

conn.

Steam

separator

Rec. line

conn.

Condensei

Test

section

Feed Watei

Rec. line inlet --

conn. (ý

Bypass

corm,

Steam

outlet

t2I

til

Bypass

conn.

Bypass

conn.

Heater

rods

r

Steam

separator

H

Control I

guide v

En

Lfl

%D

Rec. line

conn.

Figure 3.A Figure 3. B Figure 3.C

The external

core bypass

Lower plenum and core

region

Steam separator and

steam condenser
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99

1985-10-22

27

Break flow

receiver

Figure 4

Instrumentation diagram for FIX-II
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99

1985-10-22

28

0o -Steam

relief

Core

bypass

Guide

tubes

Figure 5

The nodalization diagram for FIX-II
I!

t !i

H--

t0

OD

EH

96

Figure 6

Nodalization of the recirculation lines
1-3

4100 '-4

522E

11

4 2102

026 2 --

l

33 

2102 

I

52,

32 74 o -2

31 970 3 .. o

Figure 7

Nodalization of the main volumes of the FIX-II 0

(compare Figure 3).
STUDSVIR ENERGITEKNIK AB SUSI/R8/93 STUDSVIK/NR-85/99 3.1

1985-10-22

Table 1

The test matrix for the first FIX-IH LOCA experimental period. Test No. 3027 is one matrix No. 2

experiment.

Test matrix No. 1 1 2 1 3 4 5 16

Break classification Split breaks Guillotine

breaks

Type of simulation A B C

(see Figure 17)

Break I.D. (mm) 12.0 12.0 15.0 30.5 16.0+ 21.6+

21.6 21.6

Relative break area (%)* 31 31 48 200 155 200

Initial bundle power (MW) - hot channel 3.35 3.35 3.35

- average 2.35 2.35 2.35

* Refers to the scaled down flow area of one main recirculation pipe in FIX-II compared with the Oskarshamn 2

reactor.

Brenk type A

Split break

Break type 8

Simpliriec

gui lot ine

break

Break type C

Guillotine

break

Pl~~l.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99

1985-10-22

Table 2.A

Evaluated measurement errors

32

Quantity Probable Error corresponding

error to 95 % confidence

level

Pressures 0.014 MPa 0.04 MPa

Fluid temperatures 1°C 20C

Cladding temperatures 1.6 0 C 3.2 0 C

Small range differential

pressures

(5 to 7.5 kPa) 0.13 kPa 0.3 kPa

Medium range differential

pressures

(25 to 50 kPa) 0.22 kPa 0.5 kPa

High range differential

pressures

(100 to 700 kPa) 0.26 kPa 0.65 kPa

Table 2.B

Errors in derived quantities

Quantity Probable error

Mass flow rate in orifice

meter K1 (P1)

Mass flow rate in orifice

meter K2 (P2)

Mass flow rate in orifice

meter K6 (steam flow)

Mass flow rate in orifice

meter K7 (Bypass)

Break mass flow rate

Electric power to bundle

and bypass heaters

0. 2 kg/s

0. 14 kg/s

-10 % of actual

value

-10 % of actual

value

-10 %-.of actual

value

1 % of max value
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 33

1985-10-22

Table 3

RELAP5/Mod 2 code features

COMPUTATION PROCESSING.FEATURES

- Several problem type and execution control options as

a. steady state initialisation using fictitious structure heat

capacities for faster convergence

b. transient calculation

c. strip type execution, to select requested parameters from a

restart file

d. trip system, to decide on actions during calculation due

to reaching specified conditions in calculation parameters.

e. ability to delete or add hydrodynamic components, structure components and control variables at a restart of

calculation.

CLASSIFICATION OF HYDRODYNAMIC MODEL

- One-dimensional, with provisions for

a. choked flow model

b. abrupt area change model

c. cross flow junctions.

- Two-fluid, six equation, space-time numerical solution scheme.

- flow regime oriented field characteristics depending on mass flux and void fraction for

a. horizontal flow with bubbly, slug, mist and stratified

fields

b. vertical flow with bubbly, slug, annular-mist (and stratified) fields

c. high mixing flow with bubbly and mist fields (for pumps).
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 34

1985-10-22

Table 3 con't

HYDRODYNAMIC COMPONENENTS (Input systematics)

- Volume type components

a. single volume

b. pipe and annulus, for condensed input of several similar

single volumes

c. time dependent volume, for defining a boundary source with

a time dependent fluid state

d. branch, a volume capable of two or more connecting junctions at either end

e. pump, characterized by rated values for flow, head, torque,

density and moment of inertia. The single phase homologous

curve, two-phase multipliers and phase difference tables to

model the dynamic pump behaviour

f. special system components for steam separator, jetmixer,

turbine and accumulator.

- Junction type components

a. single Junction

b. time dependent Junction, for a time dependent Junction

flow whith a time dependent or controlled flow state

c. cross-flow Junction, to model a small cross flow, a tee

branch or a small leak flow

d. valve, various operation characteristics available for

check valve, trip valve, inertial valve and relief valve.

INTERPHASE CONSTITUTIVE EQUATIONS

- Interphase drag

a. steady drag due to viscous shear depending on flow regime.

Semi-empirical mechanisms to describe flow regime transitions

b. dynamic drag due to virtual mass effect.

- Interphase mass and heat transfer depending on flow regime and

the fluid fields to saturation temperature differences
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 35

1985-10-22

Table 3 con't

FLUID TO WALL CONSTITUTIVE EQUATIONS

- Wall friction due to wall shear effects formulated for flow

regimes and based on a two-phase multiplier approach.

- Wall

for

heat transfer depending on flow characteristics defined

a. single-phase forced convection (Dittus-Boelter)

b. saturated nucleate boiling (Chen)

c. subcooled nucleate boiling (modified Chen)

d. critical heat flux (Biasi or modified Zuber)

e. transition film boiling (Chen)

f. film boiling (Bromley-Pomeranz and Dougall-Rohsenow)

g. condensation (partly Dittus-Boelter).

- Interfacial mass transfer at the wall depending on wall, fluid

and saturation temperatures for

a. subcooled and saturated boiling

b. transition film and film boiling

c. condensation.

HEAT STRUCTURES

These may be rectangular, cylindrical or spherical in shape.

The structure position is defined through component numbers of

left and right hand side hydraulic components. A structure is

physically defined by the geometry and the temperature dependent

conductivity and volumetric heat capacity data. The structure

model is further specified by the number of internal mesh points

in the direction of heat flow.

CONTROL COMPONENTS

By these new (control) variables are defined from calculated

parameters using algebra, standard functions, trip type operands or integrals.
Table 4

Initial conditions, measured for test No. 3027

and predicted (Data for test No. 3025 within

parenthesis).

Pressure in the steam dome

Power to the 36-rod bundle (incl

connections)

Power to the bypass heaters

Cooling power in the filler body space

Mass flow rate through pump P1

Mass flow rate through pump P2

Mass flow rate in the bypass

Mass flow rate in the 36-rod bundle

Mass flow rate in teh spray line

Mass flow rate in the feed water line

Temperature of water at the bundle

inlet (TE2)

Temperature of feed and spray water

Water level in the spray condenser

(Fig 6)

Rotational speed of pump P1

Rotational speed of pump P2

z

0-

Test

MPa 6.96

MW

kW

kW

kg/s

kg/s

kg/s

kg/s

kg/s

kg/s

0C

OC

m

/s

/s

3.425

65.7

264

4.85

1.60

78

5.67

5.10

2.54

267

179

.791

27.16

35.57

(7.00)

(3.385)

(57.4)

(196)

(4.56)

(1.55)

(.71)

(5.40)

(5.36)

(2.49)

(269)

(181)

(.815)

(25.46)

(33.42)

Prediction

6.98

3.385

57.4

207

475

1.49

.61

5.62

5.36

2.49

268

180

.825

26.89

35.32
Table 5

List of events in test No. 3027 and in prediction case A

within parenthesis).

(Data for Test No. 3025

cn

1-4

LII

z

LII

0

1-4

H

LII

Time (s)

Event Imposed action System reaction Prediction

The break occurs (Valve V120 starts to open)

Start of coast down of pump P1

Flow reversal in the samll RCL between break and LP

Start of power decay in rod bundle

Start of power decay in bypass heaters

The SRV starts to open

The SRV is fully open

The first dryout occurs (level 16 to 12, several rods)

The SRV starts to close

Minimum in steam dome pressure occurs (6.69 MPa)

The spray flow is closed

The feed water flow is closed

Valve V104 to the evaporation cooler is closed

The SRV is closed

Rewetting of the first dryout

0

0.0

0

(0.0)

0

0.0 (0.0)

0.0

0.1

0.5

1.0

1.6

(1.1)

(0.4)

(1.0)

(1.6)

(1.8)

(1.9)

(2.0)

(2.3)

1.2-2.2 (1.4)

0.0

0.0

0.0

0.0

0.4

1.0

not seen

1.6

1.8

1.9

2.0

2.0

2.3

not seen

H

0,

CO

Hn

0:)

N,

%D

to

1.9 (1.8)

2.1

2.1

2.1

2.5

-J

3.5 (3.6)
Table 5 con't

Time (s)

Event Imposed action System reaction Prediction

tri

w~

Maximum in steam domw pressure (7.31 MPa)

The SRV starts to open

The SRV is fully open

The water (two phase) level reaches lowermost

part of the downcomer

Cavitation in pump P2 in the broken RCL

Flow reversal at the bundle inlet

Flow reversal in part of the intact RCL

Flasning starts in the LP

Level swell (recovery) in lower and middle part of

the downcomer

Flashing starts in the bypass guide tubes volume

Peak in teh bypass flow into the UP

Core uncovery begins at rod level 16

Core uncovery begins at rod level 7

Core uncovery begins at rod level

Tripping of the bundle power (stop signal of test)

7.4 (7.8)

12.0

12.7-78.7

(11.8)

(12.3-75.3)

14.1

14.7

15.0

24.4

23-24

24-30

24.3

25.3

45.

51.

67.

70.5

(13.9)

(14.7)

(21.)

(22.)

(23-31)

(25)

(26.7)

(49.)

(51.)

(62)

(75.2)

8.1

12.3

12.8

13.5

15.3

15.4

22.2

21.

236-29.4

25.6

20.4 and 31.0

63.

61.

not seen

75.

Ln

I)
Table 6

Main results measured for

within parenthesis).

the test No. 3027 and predicted (Data for the test 3025

tn

F'_4

C)

01.

Simple-value parameter

Time to

- (first) dryout (s)

- max rod temperature "

- rewetting, max "

- bundle uncovery "

- 2.0 MPa dome pressure "

- end of break discharge "

Dome pressure

- max after the break (MPa)

- at end of break discharge "

Experiment Prediction (Case A)

1.2

2.7

3.5

45

80.5

78.5

7.31

2.09

8.2

-4.1

-4.5

(1.4)

(3.6)

(3.6)

(49)

(79)

(75.6)

(7.34)

(2.15)

62

- 78.5

75

7.35

2.15

I f

IN Max break mass flow

- through break

- through pump P2

- from lower plenum

Integrated mass flow

- through break

- through steam relief

valve

(kg/s)

of

It

7.4

3.6

6.8

3.3

3.5

195

W

ko (kg) 222 (214)

of 40 (39.7) 39.8
Table 6 con't

Simple-value parameter Experiment Prediction (Case A) InI

Max rod temperature

- during dryout (OC) 360 (389)

- at end of break

discharge " 382 (352) -303

Position of max rod temp

- during dryout (rod/level) 10/14 (16/14) -

- at end of discharge " 14/11 (22/7) /5

ODi!'j

00

01- %D

w.

o
Table 7

Run statistics data (Case A)

En

Transient

time (s)

-5

0

10

20

30

40

50

60

70

75

Computer

CPU time (s)

0.

118.1

229.1

227.6

353.9

437.1

517.6

569.3

766.8

828.3

Number of

time steps

Number of

reduced current

Number of

reduced mass

0

200

384

455

533

612

695

759

928

982

100*

90

19

7

6

13

11

1

0

0

0

0

1

0

2

0

63**

10

I En

cn

(11 *

**

All current

Mass error

limit time step reductions was caused by core flows

limitation occuring in downcomer lower part

,Ph
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99

1985-10-22

42

Table 8

Parameters plotted and used in the assessment

comparison.

COMPONENT C'TI..NOUS PARMPTER * EXERIM]DT PI CTI1ION PLOT IDNrrIP. PLOT

(IDENTIFIER) (MI•OR EDIT) WP. CALC. NO.

......................... -- . -.-- .......---....... ......-,-............... ..-.-.................... ............-- 0.., .....

CORE FLUID DDISITY. BOTTOM

MASS FLOW RATE. INLET

HEATING POWER

t*0

OPT 4

X 801

CLAD TEMPERATURE. LEVEL 1 TE 191. TE 206.

TEE 211. TE 246

- . LEVEL 3 TE 108. TE183.

YE 243. TE 248

- - . LEVEL 5 TE 202. TE 227.

TE 232. TE 237.

YE 252

- - . LEVEL 9 rE 102. TE 137.

TE 167. TE 172.

TE 187. TE 197.

TE 272

- - . LEVEL 12 TE 118. TE 123.

TE 128. TE 148,

TE 223

* - . LEVEL 15 TE 175, TE 190.

TE 275

INLET T4MPERATURE TE 3

OUTLET TEMPERATURE TE 14

CORE INVENTORY * OPT 5 * OFT 6.

OPT 7 * DPT 8.

DPT 9 * DPT 10.

OPT 11 * OPT 12

RHO 04.01

P 33.01 - P04.01

CNTRLVAR 57

HTTEMP 4.0100

HTTEMP 4.0300

HTTEMP 4.0400

HTTEM 4.0600

HTTEMP 4.0700

NTTTEP 4.1000

TEPF 33.01

TEMP? 51.01

P 04.01- P 51.01 **

D 4

X801

TC 1

RHI? B.

PD4? B.

HPI? B.

HTZ? a.

1

2

3

4

TC 3 KT2? 8. 5

TC S HT3? B. 6

TC 9 HT4? B. 7

TC12 HT5? a. 8

TC15 HT6? B. 9

T 3 TF1?

T 14 TF2?

D CO PDC?

B.10

B.11

B.12

VESSEL FLUID DENSITY, BOTTOM

DONCOMCR MASS INVENTORY *

LOWER PLENUM MASS INVENTORY

UPPER PLENU MASS INVENTORY

PRESSURE LOSS. S.S. ORIFICE

UPPER PLENUM TEMPERATURE

DOW'NCOIE TEMPERATURE. BOTTOM

LOWER PLEN•M PRESSURE

UPPER PLENUM PRESSURE

MASS FLOW RATE. BYPASS

OPT 27 * OPT 28

DPT 29 . DPT 30

OF 2 * DP3 -

DP I

DP 13 * OP 14

DP 56

TE 15

TE 31

PT 3

PT 4

X 602

RHO 31.01

P 71.03 - P 72.01 *

P 31.01 - P 32.01 **

P 51.01 - P 52.01

P 52.01 - P 52.02

TEYPF 52.01

TDEF 71.08

P 31.01

P 52.01

MFLOWJ 117

R92? B.13

D DC PDD? B.14

D LP PDL? B.15

D UP

D 56

T 15

T 31

P 3

P 4

PDU?

PDS?

TF47

TF3?

P 1?

P 2?

B.16

8.17

8.18

B.19

8.20

B.21

X602 MFI? B.22
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99

1985-10-22

43

-COMPONENT CO"ITINOUS PARAMETER * EXPERIMENT PREDICTION PLOT IDENTIP. PLOT

(IDENTIFIER) (MINOR EDIT) EXP. CALC. NO.

-..- .... -.- ..... ---. . ....---... . ----..... . --..o --. -. ..- .-- . .... .--- .- .... .......... ....-- .....-- ...... -........ --

RECIRCULATION MASS FLOW RATE. I. L. PUMP

LINE (ORIFICE KI)

MASS FLOW RATE. 3. L. PUMP

(ORIFICE K2)

MASS FLOW RATE. B. L. VESSEL

INLET (SPOOL PIECE KIO)

X 603

X 604

X 610

MFLOWJ 201.02

MFLOWJ 202.02

MFLOWJ 97.02

X603 MF2? B.23

X604 MF3? B.24

X610 MF4? 8.25

SYSTEM

BREAK

MASS INVENTORT

MASS FLOW RATE. STEAM RELIEF

HEAT LOSS. PASSIVES

FLUID DENSITY

MASS FLOW RATE

MASS FLOW RATE. INTEaRATED

INLET TEMERATURE

INLET SUBCOOLING

INLET PRESSURE

X 607

THASS

MFLOWJ 404

CNTRLVAR 53

RHO 96.01

MELOWJ 152

CNTRLVAR 55

T]'PF 96.01

TEMPG 96.01 -

TEMPF 96.01

P 96.01

MAT?

X607 MF5?

HLI?

X 636

x 661

TE 34

PT.6

X636

X661

T 34

RH3?

MF6?

MLI?

TFS?

TSU?

3.26

3.27

B. 3

9.28

8.29

B.30

B.31

3.32

P 6 P 3? B.33

REXAPS/MOD2 COMPUTAZON CPU TIME CPUT*iE

COMPUTATION MASS ERROR IEASS

THE COMPARISON PARAMETERS ARE THOSE REPORTED AS DIRECTLY MEASURED

OR AS COMPUTED RESULTS FROM THE EXPERIMN-T.

PRESSURE DIFFERENCE INSTEAD OF MASS FLOW RATE OR OF MASS INVENTORY.

** CORRECTIONS APPLIED TO RESUME THE CORRECT PRESSURE SENSOR LEVELS.

** NO DATA AVAILABEL FROM THE EXPERIMENT.

CPU? 3.34

MAE? 8.35

STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.1

1985-10-22

• • 0ti 4IollT e011. STE......... I PRECAI.CULOTIOM 0C.'-Ot1 10.1LC 604 31v00 .0011 OII4 MARC" a0

* 2440660 00.C 101 cROUOHNESS [HAROED 0 o 01-* 000 0.6

* zo4 &PRO •O.c JUNC S201 CHANDED ROM 2.34 30 D.,6

* 24A4"0S DLC J.01 "00 oPF C¢ANkI[O FROM 1.43 10 0.34

2 

2 0 4P060 S001 00. AB001 (utoilS 0O 0T OP ! TO 9AO6 WITH 3027 0P * .PR OC000 All0 we 0 01 "'Or 10 00a' C .o • ••mk• f A ODS RD ADE ,,. 0 0 ND Of DE€K ....

S olot 0 00 POWE MEAN CORE CHANNEL 0000100 006 500*S3

0000101 It. 0000100 00. 20.

0000203 24.. I.01-4 0.01-2 00000 3 100 1000

000010? p 032010000 *PPISSIUR LO0ER P [ VOL2 00. 

0000303 .00105001 0 00400000 1O01 90L 1

0000102 P 004140000 *PR[5SUR[ COE VOL 10

0000310 0 0 00 0000 *P REPOU RE UP PER .P 0...

0000)6 P 00001M000 01[S 1 STEAO 000 001N VOLII .

20000317 P l0000 .... •PRESSURE 071A0 0001 VL0 *. 00003100 P 021000000 00R10000E 01 ANNUUO.L. VO

0000320 C00TR.V06 

040 *LIOOD LEVEL IN OC ANNULUS

0000321 VLVAR0(0 000000611 .V6LVt6 00 0 I5T00.1

I.03,3. 0000 0040I0000 •.0105D CO VOL 0

0000332 VODO 004020000 I.0. 0 COV E VOL z

0000333 VO. 0004030000 -VOID CORE 700 3

0000334 VOID0 00.040000 VOID CO0 I0L0

0000130 VOO 004050000 .V01 CORE V0OL S

0000334 004040000 .000 *-VOID COE V0OL 0

000010 VOI O 004030000 -VOID CORE VOL 0

0000330 V01Do 0040000060 *.000 CORE OL .

0000319 00V00 0040000601. . 0 , 1. 00 00L 0

0000. 00004 00401000 00000 1CO01 VOL 00

0000340 : 0000 044030000 .0000 BY.0005 OufLO|

0000042 00004 002020006 00000D 0IS00 00

0000343 0T000000 * S0000 07E40 A.00 01 0OL.0

0000344 V0010 012010000 0V00 S010TEA DO0 VOLIZ0 1

0000345 V0100 012020000 -VOID Si004 DO0 VO.2.2

000034.4 0000 020100000 0VOID 0c ANNULUS OL.

000034:1 VOO 020020007 0000D D0 ANNULUS VOL2

00003*0 00004 020036000 I 0V00 D0 TIC NUL.0 VO.3 0,0003 0 0000* 0ZI006000' 00000D 0C ANNULUS VO A

00000:0 0O000 0..000000 * D0011 BYPAS VOL0

0000300 VO000 002010000 :VOID 0400 IU00 00L

0000002 00000 012000006 *9OID 10O4 TO 0U1 V00L2

000030) 00IDO 0301000060 VOI LO0ER PLENUM 0OL.

0000304 VOIDG 094000000 'VOI0 09144 VOLUME 0000)03 0040.0 003000000 *OUSLOOO 00140 0.0N1

0000004 00060 000I0 V 010300000 PUMP PI 0.UCTIO L:

0000)30 VO000 0%4000181 -Vol0 PUMP P2 S1700. L.E

0000109 0FLOJ . 04000000 A0N00 VALVE 0000340 001L000 000000000 00SS FLOW 0T0A4 RE1.0F 000034001 "P .00 00L60000 00400 'LO 010 06 0 1 .L

o00004 0.. 00.. 0046200O06 *0ASS L00 1001 200 2

00000' 0000. 004600000 00400 0L00 1006 JU 0N Z

0000)40 00100. 004066660 004S 0 L0 0 1001, JUN I

0003660

0000364

0006306

00660349

0006336

0000370

0000070

000303)

0060374

0066330

0066370

0060337

00066336

0007031

0009366

000301

0000363

0000304

0000090

0000340

0066038

0066039

0000000

0000392

0000393

00000394

•00003 90

00000394

'0000307

•0000 0 09 •09000390

0000000

0000002

0000003

0000S00

0000000

01LOJ 1004000800 -MASS fLOW COO[ U0L0 T 0LO.VJ 00000000 .:ASS FLOW 0 1. PASS'O1L

00LO0. 020000000 000SS FL0 63-PASS OuI 0L00.J 106000000 .MA4SS 0LOW '0RM *0SR

0FL..J 307000000 . . 00SS '01W 0000 S0A"

"1FLO0 1004000000 -MASS FLO FRO S0(A0

00LOJ 0200000 .0 L0 O 01 C ANNULUS

00LO0. 020026000 0SS f OC A01 4 LUS 0FLOJ 020030000 46ASS FL0 Oc A441LUS 0106.J 0 1?2000600 19400 FLOW 0 U. PI OUL0

POPO10 000000200 ' 0LOCITY rPUJPO 00A602

0FLOJ "f0. 03020000 -MASS FLO PUMPP2 zOUOL ,P0V,0L 000600002 *PU.PZ VELOCTY (RAO0 ,

C7TLVA4 03 *STRUCTURE M0A1 LOSS C0 0T . 4 V 0 *AS4 S TRUCTUR E 0EA0 LOSS.I 0 0 G

130LVA0 55 .0071004110 00[A. 1000

0LVA1 6 00 W LOSS

C1010100 90 * .4COR 5PO o1020L0.R S 0A 70041. Po0o1

1C3M0.RA WAR S * 4000.. 01 1000E C NtRLVAQ S0 TOTAL POWER

CHITaL VAR 11) 6 AURIL* HCATELOSS

C100L004 042 LI0 I0D LEVEL IN U C f LVO 043 ., . .UOO , (0 0.L 00N OR E CN1000LVa 044 LI.U00O LEV1L 100 LOVE0 C1T07010 004 PLO0W DUAL C1ORE VOLS IN, WVAR a1s '11.OW OUAOL CORE V0•6 .0I:`104 00 :LO W O VL CO ( VOL

10I.00.0 001 *OLOW 000. " COe VOL0

C"906.04 001 *FLOW 0u0L C101 VOL0

C.I00LV1- 009 t LOW 0U04L 1061 0.O0IO

PUMP DUMMY TRIP

000[ 0 OT NULL 0 0. BY-PASS VALY IC RIP5S 0FL00J 017000000 0 4ULL 0 0.40t 0FL00J 003000000 0. 0ULL 0 0.S99 a upTI RE TRIPS 0I70 0 00 0UL0L 10

0001 0 L0 NULL 0 00

10

LET

0O", .0.11 VOL"I

DO0 V00L2-0

JUN JUN 0040000 VOL4 0 PIP0

to 0040000 10

7 0040101 0.0 10 ES 0640300 0.3.6 00 00040000 O,0002234 00

1 0040000 90. 00

PLENUM 0050001 0040900 0. 0.0103 00 6.60 0.40 2 0.00 0.00 3

0060002 0.49 0.00 9

0040000 00 00

0040000 0000 9

PL10U0 05100006 001.0 000010

0510001

0520000 VOLS2 PIPE 0000001 2

0420000 0.0 2

0000200 1 0.002034 

0520301 0.020 1 0.953 z 0020400 0.0060 1 0 0.00340S 2

L -USED AT 4 r0A10 5 0020400 90. 2 0000001 0. 0. 2 4 •051409 10401 0%00090 2.06 0.04 0

k -STE.., 5i040 0020000 00 2

0521101 0000 1

L •STCADY STATE CAR •iiiiiiiiiiii..ii..iii.i L 4NULUS 0110000 V0LII 

0i00020 0

000010 0.40

011000 0.00930 1

0100000 90. I

0. 0* .003 06 001000001. 0. 9111001 O

01*0000 V0 0 LIZ IPE 0020000 001.02I 00011

6. O.0040 60 00201001 002000l 00 0.0 2 2

00:0300 2.200 1 0.110 2 0102000 0.43200 I 0.024l00

0. 0.0003 00 0020000 90. 2

40,0000 00 0 00 2

0102101 0 000 I

.ii.....................

0.0s 0.00 3 0.00 0.00 0

90. 0.009 0. 0.0017 00

0314000 VOL 1 .... C.

0000000 0. 0.000 0.00'*) 0. 90. 011.0

01020003 01.02 00441

01200001

0102,00 . 0.020 0.000.' 0. 90. 0.3Z2

0000000 000.30 0901LV0L

0300000 0. 0.220 0.00200 0. 90. 0.170

0030000 R0O.03 04GL0L.0 010300 3.S,0 0.01411 0. 00. ).%. 0. 0. 00 0%11014 %rail CA

60:0000 VOL. A40ULUS

6010000 4

The stady state input
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.2

1985-10-22

0010101 0.0 .

0o10o0o 0. 0 0.033037 0o. 3 0210301 0.*0. I O.3lO 0 0 700* 0.164* 0230600 o.00,09 1 0.040003 0 o.o09.5 3 0.005721

0 -90. .1000 1 02100,0 0. 0.3000 0 O° 0.2609 2 0. 0.5100 3 0. 0.100Y

0010900 0. 0. I 0.9* 0.96 ? 0. 0. 3

0111001 00 9

0110131 1O e010000 00100 PI

0010001 VO0 P[

0700101 *0. 0 0710301 0.9900 3 0.0190 .

01100000 004* 1.01007T 0

0.101060 0. -90. 0

01000 0 . 0.O. 8 1010001 0.00 0.00 2 0.10 0.30 3 0.00 0.00 0

07o1001 00 0

07 301 010)10 I

0790000 017 1 1 . 20C.

1010001 0

0170)0 1 0. 0.300 0.002003 0. .90. -0.100 0. 0.

0130000 OL3 PI0LP0E 0030001 0. 3.2.0 0,033?' I0 -90. .0.730 0. 0. 00

00.0000 S 0ol * P)P[ 01700001 3

0040101 0.00 3

0100201 0. I 0.00"341 ? 0. • 0040300 0.333 I 0.300 2 0.000 3 0.300 0 .0.13 3

070.0.0 0.01340 0 0,00073 2 0.00223 3 0.00023 0 0.00206 3

0640601 90. , 0 0* .90. 

07600001 0. 0. 4 o0 0,0.0A ? o1,oo01 0.7 0I .00 3 0.09 0.09 2 0.22 0.22 3 0.00 0.00

0@11001 00 3 0701101 I0000 I 1000 2 1000 3 11000

0*20000 001*? 3mG190I 0701000 0. 0.203 0.0302? 0. -90. -I.220 0. 0.

00600030 001.. oiP0

00*0000 0

0*0|010 0.0 3

0*00303 1*067 0 1.333 2 0.300 3

060.001 0.001100 I 0.003*3 2 0001150 3

01060*0 90. 3 0*I00000 0. 0.0*00 I 0. 0.0*72 2 0. 0.0*10 0

0*00901 0.00 0.00

00.00001 00

0641101 1000 2

11010019 COCUL .TI4 N 10*LI

19100000 30L.9 I 00C9 0910001 0

0900101 0. 1.•06 0.00500 0. 0. 0. 0. 0. 00

0090000 V0L92 5N0LVOL

091000 0. 0.330 0.00300 0. 0. 0. 0. 0. 00

0940000 V0L9* S0LV0L

0900103 0a . 1,WR 0.0023* 0. -"S. -0.0.0 0. 0. 00

00 ... ............

0930000 30O.93 OOOOCO 095000| 0

0930003 0. 1.690 0.003*b 0. I*.3 0.010 0. 0. 00

0960000 VOL96 +R69CH 09*0000 0

09.0101 0. .400 0.006Z9 0. 0. 0. 0. 0. 00

0900000 0 7VOL PIPE 0970001 03.

0970100 0.0 3 0991030 0.709 0 1.622 0 0.210 3

0010900 0.00330 0.007 .. 2 0.0020* 3 00090603 3. 0 0. 0 -90. 3

0970700 0.*61 I 0. 0 .0.200 3

0970001 0. 0. 0 0. 0.00*0*0 3

3970900 3.03 1.43 1 0.00 1.09 0 00 09170003 00 3

0973001 0000 1 0000

20e0000 POOP) Pri-P

2010101 0. 0.030 00.1010 0. 00.0 0.103 0

2010100 073010003 0.000.. 0.01 0.31 0000

2010100 010000000 0.000900 3.00 1.00 0000

100Sa01 1 4.36 0. 0.

2010700 0 •*s 0. 0.0 2030301 0 0 0 -l 0 n

201010? 300.49 0.390390 0.0003 30. 00.0 1. I0000.

2000103 0. 0. 0. 0. 0. .111 •O"OLOOA PW.P000000. 0004 009610 7009 *316-A7000 000130.00

t 0o0, .0L0l0094 A 3006 0037003.3? 0 0107* O L O 0 390

* 0007010.310* 'PAYS; ..... 10 (- 3 0006 DAA0 0-0*0. 011100 1 0 100000) 0.00.1.001 0.27*.0.00 0.071.I1*0

"0III0 AT 01.1 300.1.000

1.1110. ,1

z01 001 0.00.0.04 0.09.0.00 0.10.0.00

2000300 0.30.0.90 0.`9,009*. 0.00.0.99 1.00.1.00 ?0000300 I 2 2010300 0.0.-0.3*0 0,41.-0.34 0,51..0.03 0.70*.0.o

0011302 1.00.1.00

201110 0 1 0

0011300 0.0.-11*0 Z .9.0.o0 0.40.0.31 1,0o.1.00

2001300 I 3

1011001 -0.00,0.00 *.9...01 *0,0.1.3 -1.30.0,39

2011030 0,00.0.00 ?000000 1 *

201100 -l,0.0,00 -0.P9.0A3S -0M43.LTI5 -0.30,T.93

201a102 0.00.0.70 00|1000 2 3

a013001 *0.00.3.30 -0.03.0.00 -040.2.00 -0.34.le93

0001012O 10 3 0...9 -0+.2.1.09 4000.0.99 0.00.0.0 . 0000000 0

2000003 -1.00.3.30 -0.09.0.00 -0.99.2.3? *0.40,2.04

-A0*1,43.1 a0100 0.001.06 6 O 000 P043[ 0911I3PL.31 V60L13

2012000 0

Z003000 0.0,0.0 0.3.0.0 0.35.0.00 0.24.0.0 003.0.*0 0.•0*0.9

0003000 0.4.0.00 0.60.09 0.9.0.0 0.*,0.io 10.0.0.

0011100 0 2013101 0,0.0.0 0.1,0*0 0.05.0°05 0.0l0.0. 0.3,0.0* 0040..00

0013100 0.4,0.90 0.*0.0. 0.9.0.0 0,9*0.1, 1.l0.00

I PPUNP 0WO1RMoC1 FOR 70. psOPP 00*D I.;C.I-olC0

0010100 0 I

20,0 .0.000.0.0.0 001.09 0310 0. ..0.19 .0. 03 0000..

0 0..0 0.110.000 

2006203 0 -0.010 0I1-0.001 0.0.0.0 0.3$0.1 0.0.00 0.0.0.0c

2004000 0.9.0.00 l*0.1*0 0030300 I 3

,01,302 -0.h. *9=1 -0,.* *0,-. 0.06.00 st0at. 

?001600 0 a 201.000-1."0.-I.10* -0*+,-0, 0

0 -0.1.-0.3 -0.7.-0.33 -0.*.0.-071

203*00? .0.3.-0.00 -0.33.0.0 -0.?0.0.0 -0.+.0*00 0.0.0.00 O lu POmlS 0I1F?(01C1 700 puOp 000000[ 0. 310013 P9030. ..01C" 01693

O Ol**? 0ULL? 0(006010 000001 I 01000•

0 -010f00 $ 2000900 0.00.0.00 0.09.0.00 0.19.0.09

?000900 0.3I0.057 0.39.0.900 0.00.0.99 0.00.1o09

2 -013000 C

0010001 0.0.-loi* 0,5.00.0 0.161.0.)0 .00.1.00

0033000 -1.00.3.3J0 .O01.03.70 .0.060.2.9 .0.30.1.93

0013100 -0.,37.0*.09 -0.00,I*I9 -0.10.0.99 0.00.0.00

7013000 -0.01.3.31 -0. 79.0.7i -0.30.2.31 -0.03.0.00

2003200 -0.2I0.1.7 0.00.1.33

001*100 301 C0001060 003 *317.0o 316r1 C*0U

201*101 0. 0. 31000. 0000. 037faj~o 30477 C660

••P4.03 COfmO~l 3,37f0 030740? 90601 C600

?0030000100 0710OfF 379 1000. 0. 0 .307.07 30001 CAOO

20300100 0.34 -1.0 01106J 100100000 13016100 51&11 C

?0030000700 00l010~ 10070001 0. 0. 0 0$11100 3il00 CO"l
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.3

1985-10-22

20.00200 CW0.. V&. 00. 20500300 V10.DIF0I SUR

205003001 04.543 0.0 1. 0.

C¢0I;0LA 002

-ST1010AD 0Al CARO

I *71000 5001 CO ., 51IEISS,.Ar CA 0

2020000 Pw•p2 P099

202000 ' 0. 0.100 0.00500 0. 72.0 0

202000t 094010000 o.009, 0.35 0.32

202000 09000000 0.000360 3.06 3.0a

?020200 0 0.55 0. 0. 2020202 0 0.55 0. 0*

20Z0301 0 0 -l -0 0 0 0

2020102 303.69 0.7300;4 0.01050 25. .

2020303 0. 0. 0. 0. 0.

2021100 1 1

2021101 0.0 10.13 0. I '.s35 0.4 0.020

2020002 0.6 1.100 0.0 0.5 00 0.000

2021200 2 0

2020210 0.0 0.51 0.0 0.00

2020300 - 2

Z020300 0.0 -0.540 0.2 -0,305 0.4 -0.0

2020302 0.0 0.4. 5 0.0 0.545 0.0 1: 000

20210400 2 2

2020400 0o, -0.4 0.2 -0.20 0.4 0.07

202M402 09. 0.35 0.0 0.40 3.0 0.

2021050 0 3 2021050 -•,.00,2.00 -0.95.10.0 -0,62,0.S1 2020S02 0.00.0.034

2020400 1 4

20204 -0.00.2.00 -0.79.1.53 -0.63.1.25

2020402 0.00.0.72 2020700 2 3

2021701 -".00.3.31 -0.03."270 -0.0.2.29

2020702 -0.37.0.49 -0.22.I0.0 -0.I0.0.99

2021800 2 1 2020000 -0.00.3.30 -0.79.2.70 -0.59.2,37

2020002 -0.20,.0.1 0.00,0.55

0O23000 0 2023000 0.0 0.000 0.0 0.00 0.2 0.05 0.3 0.00 C

20?3002 0.4 0.90 0.0 0.90 0.0 0.00 0. 9 0.50 2023000 0

M023100 0.0 0.00 0.0 0.10 0.2 0.15 0.3 0.24 0

2023002 0.4 0.40 0.7 0.00 0.8 0.90 0.9 0.96 100PUM2 0100U. A000

2026100 S0o- CO1ILVOO 000

?026101 0. 0. 1000. 0000

0• 02 CON0IROL90.Sys

20500.00 9A0S01F? SU. 1000. 0.

20I00401 1. -0.0 202020000 17L0 .. 

20500000 0100L0 09010,.L 0. 0.

20500500 190L1940 004 20100400 91100772 504 h. 0.

20100400 220.0? I.0 C900LV000 00,

1010000 .UN)I0-32 SN.LJUH

.220 0

0000

0000 1010101 031010000 032000000 0. 0. 1000301 5 4.03 0. 0.

3.2 0. 00014020100 J1J932-33 SNOLJUN

102000 032000000 033000000 0. 0.

100020 01 5.0. 0. 0.

1030001 J.033-4 $ SNGLJUN

1030101 03300100 004000000 0.000473 0.430

0.5 -0.055 0030200 5.50 0. 0.

0040000 J3040-;50 SNOLJ JN

1010401 00400000 050000000 0. 0.10

1040201 3.5 0.74 0.

-0.50.1.39 I

1000000 JUNSI;OS2 SN00LJU0

0050100 050100000 052000000 0. 0. 00.30.0.93 0 o.35 1.76 0.

1 060000 JU452-Z20 SNGLJUN

0.00.0.51 1000101 052000000 010000000 0.03318 1

S. 00200 0 ,35 176 0.

.010000 .40I -201 SNOLJUN .4 0.96 O.s 0.90 0 1000 4 904000000 0200605 0.0 0.0

1.0 0.00 10002001 7.0 -0.74 0.

o.: 0.30 0.s 0.40 . .

1.0 0.00 0000 .3N192-I0 SNOlJUN S5TEADY 07I71 CA 0000000 002000000 00100000 0 *50[000 50001 CORD 1000?0201 7.02 -174 0

-STEADY 51011 CDe , S , AT ., C.,•

0 .5So01 50471 C10l 1100000 JUN40-0)3 SNGLJ5 N -STEADY 51007 C A 0000 0020100000 013000000 0.00.43. 0.95

0 510AI0 50107 Cskl 0000200C 0. 0. 0.

Ie-STEADY I At,[JO STATE CAR- * ( l 5 1I CA' .100 U? 21000 c000 'I 10 0*'00100 57001 CO 100 JO17 5GJ/

0000000 0200000 010000000 0. 0.00

0002 I001 0. 0. 0.

lllel JUe .11 1 1 0020000 JUm?0-72 5NOLJU0

0020100 000001000 072000000 0. 0.

11202010 0.14 0. 0.

0030000 . .3.. -03 150.40.. 0030191 00'2000000 07300O0000 0.00 0

11003010 0 4.54 0. 0

0. 1100

0. 1I00

4160000 JUNY4-31 5NOLJU4 0.200 0000 1004101 074010000 03010000 0. 0.00 0.00 i000

1100200 1 4.56 0. 0.

.010 0000 0070000 BY-PASS VAILV

0070001 032000000 044000000 0.000580 0. 0. 0000 0070200 o 0.40 O. 0.

0000300 0000VLV mOTONVALVE IN OY-PASS INL0 T 0000300 0000503 0000502 0.02 0.1924

0. 0000 ?000000 0.0 34.20

0070400 .000 .000 .000 .z25 .0906 .0906 .200 .1301 .1301

20004 .500 .1955 .195S 1.00 .203 .2030

1. 0020 1100000 joNso6Z SN0L0JUN 1100100 046000000 062000000 0.00474 0. 0. 1100

0i0020 0,. 0.

0.0 1000 1200000 JUN64-501 SOLJUN

0200001 044000000 051000000 0.001090 2.00 2.00 0000

0200201 1 0.60 0. 0.

0. 0000 1220000 JUN42-90 S5GL0 1

1220101 07?2010000 001000000 0. 0.00 0.00 0100

02202001 0.5 0. 0.

0.95 1000 -1STEAY S0 1230000 4N99- $901400

123000 090000000 040900000 0. 0.00 0.00 0100

123020. 15 0. 0.

1.00 1000 1240000 JUN91-92. 1501JUN

1240101 09]000000 092000000 0. 0.00 0.00 0000 02402001 0. 0. 0.

0. 0000 0250000 J0595.9 NOL7 NU

025000 095000000 090000000 19.0f-4 02.5 02.5 0000 02512001 0 0.9 5 0. 0.

0. 1000 -12:0000 JUN9910.946 590L4JU

*020000 091000000 094000000 0. 0.00 1.00 0000

S12002001 0. 0. 0.

0770000 09U50-94 SNGL5JUN

1270100 095010000 09600000 0. 1.00 1.00 0o00

1270200 0. 0. 0.

0210000 N09730 .5014OLJUN
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.4

1985-10-22

ozoooo1 oooo10o00 oioo10000 0. 0.00 0.00 01000 0?00700 0 0.55 0. 0.

* COOLIN 5150(9G 

3020000 COOO IN1 TIoOPYOL

301000 0.0959 0. 0. 0. 0. 0. 0. 0. 10 3010000

3010?00 0. 7000000. ,404000 0113010000 3040000 0. ,(000DY 000 S

*4040700 0 0. 0 a 0. *STEADY S+T[ CANO

.010000 COOLING 715PJUN 4 DU"p V.OLUMES

4000000 077000000 301000000 0.

4010000 1 S04

40007 0. 7.05 0. 0. 1.74 ?.05 0. 0. 2.0 0. 0. 0. 5020000 0U733 7000vOL

0.00 1.50000 000 0. 0. 0. 0. 0. 0. 00

•.5020000 I

3070000 S9081FLOw 77DPOL So2020o 0. 100000. 0.0

)070101 0.007575 0. 0. 0. 90. 0. 0. 0.0Z.. 100

3070700 3 " !PLT OUpTURE 04I C RCULAIION LINE 3070?00 0. 7500000. 454.0 IIOiI l24leli

........ 0: SO

1520000 0(0AK VALVE

4070000 SPOIOFLOV TMDPJU7 4 0570000 096000000 507000 0 0.0001131 0. 0. 0100 9 0.s 0.05

40,001 3070100000 01?0100000 0. 0520700 I 0. 0 0.

4070700 5204 10TI.LV 0570300 

.070201 0. 5.36 0. 0 0.45 5.34 0. 0. 1.9 0. 0. 0. 0520301 0000504 0000SOS S.00 0.0 *0PIl0O TIME .20 SEC

3030000 SUOCOOO Lt TmDPVOCO 74(47 c STRUCTURES

3010101 0. 0900115 0. 0. 0. 0. 0. 0. 0. 10 14010000 1 7 7 0 0? . CORE

3030700 3 04000000 0 0

3030700 0. 7500000. 454+.0 04010000 4+ 0.004775 7 0.000025

, 0 40100701 0 -7 '

04010030 0.0 4 0.0&

4030000 5U0C001 96 I0,PJ7UN 10000400 0

4+030000 303000000 070000000 0. 040010400 570. 7

4 030700 i 504 04000500 0 0 0 0 03.740 1

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0 4000700 0 0.0744+ 0. 4. 0

•S51AN I(10EVr 1'0400900 00 0.00747 0. 0. 0

040700000 0 7 7 0 0.

• '0407000 0 0

0.100000 PELI~ mPOl VPO . I20407000 * 0.000S]75 7 0.004075

3040100 0.010*34 0. 0. 0. 90. 0. 0. 0. 00 .0T(400 57104 I'0407070 I0 -7 4

3040700 7 040720300 0.0 4 0.0 4

4040700 0. 7000000. 0.0 *50E007 STOOL CAVMO 04070400 4000

•0I0700500 0 0 0 0 13.7420 0

• 40440000 00L0fF VOLVE *OLD N0OlEL 04070400 004070000 0 0 0 13.7404 0

•4040101 010300000 304000000 0.000054 0. 0. 0000 *010 "00(0L 10407070 0 0.0030 0. 0. 0

• 4+040700 I 0. 0. 0.,01 * 00(0 .[ 04070900 00 0.00147 02. 0. 0

•10403000 0010 I .,Y •m0111y.Vi O •010 MO00(1 04030000 0 1 7 0 0.

01040301 0010040 000040. 3.332 0. "00.0 4001(0. 04030000 0 0

04030000 * 0.0047 15 7 0.004075

04030700 0 4 -7 4

042030300 0.0 4 0.0 4

.040000 00.40(9001 490LJU9 *500•401 50000(04 0• 4030400 4000

14030'200 0 0+ 0+ 0 13.?.02 I

04030400 004039"000 0 0 0 00.749 0

04030701 0 0.0034 0. 0. 0

04030900 00 0.0194? 0. 0. 0

140.0000 i I' 7 I 0.

04040000 0 0

04040000 4 0.00430%" + 0.004075

14040700 0 4 -7 4

14040 30 1040000

04040500

14040400

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14090901

14050000

14050100

04050400

04050500

10405040

04+050700

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14000000

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0 407 040

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04000000

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0 40080900

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S4 09 0900

041000000

042001000

041001000

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0.0 4 0.0 4 40100

0 0 0 0 03.740

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0 0.0000 2 . 0. 1

10 0.01747 0. 0. 0

4040

4000

0 0 0 0 13.744

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0 0,*090 0. 0. I

10 0.01747 0. 0. 0 0 7 7 0 0+

04030

4010

0 0 0 0 13.240

004040000 0- 0 03.740 1 0.I033 0. 0. 0

t0 0.01747 0. 0. 1

0 7 1 . 0. 4030

4010

0 0 0 0 13.740

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0 0.0030 0. 0. 0

1 y • I

000.007475 0. 0.0061

0. 7 .0 0

4010

0 0 0 1 03.740

004000000 0 0 0 0 3.7'40

I 0,0074 0. 0. 1

10 0.01747 0. 0. 1

0.. . o f 0 I

4 0.004975 7 0.001075

0.0 4 0.0 4

4000

0 0 0 0 03.740

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1 4,0077 0. 0. 0

00 0,00714? 0. 0.0I

0 7 7 0 0.

0 0

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4010

0 0 0 0 0.4 O1004000000 0 0 03.21"740

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$I

I

I
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.5

1985-10-22

1000020a

10650301

106s0000

100I0 03|0

10650301

106 0060 | 00070|0

1000001

106050100

1::06:0¢0

10060901

I 014600!0

10601070

10600000

10601030

S0060 000 100600501

00000901

2 I a.. 1

0

0 0 0 0 2.67

06401o0000 a a 2.27

2 0.23 0. 0.

0 00 0. 0. 000 89 PEA? AND pDOA STOUCtUO[ 7040 SAME

I 2 2 1 0.

0:41 040

0000

o 0 0 I 2.6?

064000000 0 I I 2.4?

2 0.00 0. 0.

a 0.01762 0. 0. 1 2 2 a 0.

0600

0600

O 0 0 I 2.6? 060000000 0 I a 2.4?

2 0.27 O. A.

0 0.01742 0. 0.

2020a300

20200001

20200000

2020006 a

20200700

2 02 A 07 0 a

20200000

zozooaOa

20200900

2020090 a

202. ago, 20 20 a so a

TE"P

TEMP

0. TEMP 02.

TEMP

0. 4000o0 b o0x WALL 00 0CCOUNT FOR mEAT LOSSES ao000000 10 2 I a 0.

14000100 1 1

Il000101 0 0.002 14000201 ) 1 11000301 0. a

I*000401 033. a 16000002 300. 2

14000301 001 -a 3000 0 0.1 10 Oo0a0o0o o04010000 010000 a 0 0,1 a0

140000701 0 0. 0. 0. 10

140000901 0 0. 0. 0. 30

7OFNER.L TABLE GIVING NEAT TRANSFER COEFF. AT OUTSIDE O' O0A MALL.

20200000 HTC.P

20200001 0. 1.7213[3 * OETEOMI0.D G0I O Ev[ 1055 L0SI OF APP

O 01.0001. 0AOL( GIVINO THE TEMPEOA0URES AT ImE OulSIDE 0 fmn

000 001...LL, I(.P(ORAIUE Is SUPPOSEO 00 0VAR LINEAMLY SWTWEEM 403 K

AT IMLEI 00 090K AT 00T0LET.

20240000 floP

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20200100 0. 410.0

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20210001 0. 020.0

20240000 loop

20200.01 0. .00.0

131000000 1 1 a 0.00 331001000 * .15 2 0.00

13100101 0.003 I 0.013 2 0.00 3

aII00o01 3 3

13001031 .0 3

13100501 31010000 0 a 0 .I79 a )1300+00 -13 0 030| 0 .IT9

"Il007 1 0 .0 .0 .0 I

13I00801 0 .0 .0 .0 I

ol?00000 a 0 2 1 .132

13200100 0 2

13200101 0.005 0 0.0IS z 0.01 3

13M00201 3 3

13200101 .0 3 132000101 360. 0

I3200301 32010000 0 I I .32?

13M00501 -13 0 3013 1 .323 1

13200101 0 .0 .0 .0 |

13200001 0 .0 .0 .0 I

13000000 I 0 2 I .112 10300100 0 2

I]300|01 0.003 1 4.016 2 0.03 3

13300201 3 3

M3100301 .0 1 I3300,01 300. 0

13300301 33019000 0 I I .200 3

13300601 -01 0 3014 1 ??21 1 I))007a1 0 .0 .0 .0 1

00300•00 0 .9 .0 .0 I

10000000 I ) 2 I .I|2 10300100 6 0 

110010" 2 .102

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010101:1 .0 2

15100401 300. 3

aSOaOOl 31010000 0 1 I .379 3

I?100001 6 iS 0 3010 1 .119 0

a52007O0 0 .0 .0 .o0 1

13300001 0 .0 .0 .0 1

1SZ3O000 I 3 2 3 .053

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0SZ0101 2 .0",

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IS 2103I .0 2

1503210| 1 60. 2 IS?1020O 32010000 0 a I . I3? 3

1 522000 0 0 0 3 1037

ISZ?0So 0 .0 .0 .0 a 13230001 0 .0 .0 .0 3

153220000 I 3 2 3 .030

I32M0100 0 3

13210101 2 .012 1332020a 3 2

153220301 .0 2

10?z0•01 360. 4

11220001 32020000 0 1 1 .933 I 103220001 0 0 0 I .93]1

31.0110, 0 .0 .0 .0 I

11.1000a 0 .0 .0 .0 ?

llI00000 3 0 2 3 .230

31000100 0 2 11100101 0.003 1 0.015 2 0.033 3

111.0OI3 3

11100303 .0 3

11a10401 S60.

11200101 13010000 0 1 a .oo . 1 lll0060l -3) 0 3010 3 .0530

I1100101 0 .0 . .0 a 12100001 0 .0 .0 .0 I

II+I0000 I .+ 2 I . 11210100 0 2

11?200I0 0.004 I i.0s0 2 0.030 3 II+I0201 3 3

IIZI0301 .0 3

121000 I 1 60. 11210001 I?010000 0 I 1 2.200

11210601 -13 0 301. 1 2.200 11210001 0 .0 .0 .0 I

11+10+01 0 .0 .0 .0 3

11220000 I 0 1 1 0.00

3I220101 0.003 I M.0i0 2 0,033 0

11220203 3 3

11220301 .0 3

31120301 32023000 0 I 0 .+000

If?20601 -I0 0 3010 0 .100 1
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.6

1985-10-22

0l220701 0 .0 .0 .0 0

II220001 0 .1 .0 .0 0

121101001 I2120000 1 4 2 0 .250

12220101 0.,05 I 0.005 2 0.03) 3

1210200 3 3

020000) .0 3 02100011 5411. 4

1 001 2"I'S'I 10000 0 0 0 .004 1

12100601 -03 0 3014 I .S40 1

0120001 0 .0 .0 .0 1

12110001 0 .0 .0 .0 1

02120000 1 4 z 1 .130 02020000 0 2

12120101 0.0.10 1 0.05 2 0.033 3

12120001 3 3

12010301 .0 3

020205.0 2I000000 0 0 0 .545 0

12120601 -13 0 3014 1 .509 1

02020701 0 .0 .0 .0 1

1Z120001 0 .0 .0 .0 1

12130000 1 4 ? .03Z

12030100 0 2

1Z130101 0.005 0.6.0S 5 2 0.01 3

02130201 3 3

12130301 .0 3 12130401 500. 0

12100501 2030000 0 0 0 .206 1

1213000 -013 0 3004 1 .2046

12130100 0 .0 .0 .0 0

12130001 0 .0 .0 .0 1

12040000 0 4 2 1 .032

12010000 0 2

1t140000 0.105 0 0.005 2 0.00 3

12102001 3 3

IfllOftOl .0 z

0214001 60. 3

12100.00 540.00 4lo

2100100 20100000 0 0 0 . .006 ?

1710200 0 "I3 0 30 14 0 .004 0

11102001 0 .0 .0 .0 0

17000000 0 3 2 0 .0540

071000000 0 I

071001020 3 2OO

07000300 .0 2

07000000 540. 3

07000500 70010000 000000 0 I 0.5504

17100•02 70000000 000000 I 0 0.020 0

17100401 -03 0 3014 0 0.9500

10105402 "13 0 3014 0 0.020 0

07100700 0 .0 .0 .0 0

17000A00 0 .0 .0 .0 0

17200000 0 3 2 0 .0540

17200100 0 0

17100101 2 .0707

M7200201 3 01200301 .0 3

07200000 540. 3

17300500 72010000 0 1 1 .300 0

17200001 -13 0 1000 0 .300 0

T1200701 a .0 .0 .0 1

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17300000 1 3 2 0 .0540

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17300301 .0 2

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07300500 ?3010000 0 0 I .16 1

17300400 103 0 3014 0 . 116 0

17300901 0 .0 .0 .0 I 017000000 0 .0 .0 .0 0

17100000 4 3 ? 0 .0469 070000100 0 1

17400001 2 .0445

17000201 3 2

17000301 .0 2

07000401 50o. 3

17400500 74010000 0 1 0 .57y

1?40060O0 74020000 0 1 I I.017 2

07100503 71030000 0 0 I ?2.74 3

17000504 74040000 0 0 1.500 4

17400601 -13 0 3010 . .573 

0100'402 -03 0 300* 0.007 2

17000403 :13 0 3004 I 2.071 0

07000404 -03 0 3010 I 0.500 0

7!000700 0 .0 .0 .0 0

17400001 0 .0 .0 .0 0

07.50000 1 3 1 1 0.00

170SOLO0 0 a

174"0101 2 .003

11050201 0 2

17450301 .0 2

07450000 560. 3 07450500 74050000 0 1 5 .055 0

I705000 *I3 0 0004 0 .0.5 I

07650000 0 .0 .0 .0 1

17150001 0 .0 .0 .0 1

16200000 0 3 1 1 .0415

162O0100 0 0

1020000 2 .099% 00200701 3 2

102003001 .0

10200,00 540. )

16201500 62000000 0 1 0 1.201 0 10200601 -13 0 3014 1 1.221 0

16210701 0 .0 .0 .0 0

16200001 0 .0 .0 .0 0

16400000 3 3 z 1 .0406

16401100 0 1

10110101 2 .0572

16400201 3 2

10400301 .0 z

16400401 560. 3

16400500 64010000 0 1 1 1.440 I

16000502 64020000 0 0 1 1.335 2

16400503 6.030000 0 1 I 1.363 3

01000000 -03 0 3014 1 10.10 1

16400402 -13 0 3014 1 1.3)5 2

1640003 -013 0 3014 1 1.363 3

16400701 0 .0 .0 .0 3

16400801 0 .0 .0 .0 3

10000000 1 3 2 1 .0349

10100100 0 0

19100101 2 ..044S

19100201 3 Z

19100301 .0 2

19100401 560. 3

1900501 91010000 0 6 1 0.244

05100400 -03 0 3014 1 0.24 0

M5100701 0 .0 .0 .0 1

19100001 0 .0 .0 .0 a

01200000 I 1 2 1 .0369

19200100 0 0

19200101 2 .044S

19200201 3 2

19200301 .0 2

19500401 560. 3

19200500 92010000 0 a 1 0.335 I

05200400 -03 0 3014 0 1.339 1

19200701 0 0. 0. 0. 1

19200401 0 0. 0. 0.:

19400000 1 3 2 0 .0206

19400100 0 1

19500101 2 .0301 09000200 ) 2

051007030 .0 2

10500100 540. 3

19400%01 9.010000 0 I 0 I.184 1

19400601 -13 0 3014 I .1008 1

19000701 0 .0 .0 .0 0

19400001 0 .0 .0 .0 1

0550o000 0 I 2 0 .0746

1M500100 0 0

195500001 z .0300 19500201 3 2

19500101 .0 2
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.7

1985-10-22

19500401 540. 3

19000001 I 95018000 0 0 1.40 19500401 -03 0 3014 I 1.483

I0$00071 0 .8 .0 .8 I 10500880 0 .0 .0 .0 0

19400000 I 3 7 a *0305

19000108 G I 19400100 7 .0445

19000A:1 3 :

19400301 .8 7 094004601 54P0.0 3

19m0020l5 9010000 0 1 1 1;475 1

194000)1 031 0 3004 0 .4751 19400701 8 0. 0. 0.

19400000 0 0. 0.0.

I9310000 3 7 0 .024'

19730100 10

0970001 7 .0302

197I0,01 3 ;

09700300 .0 7

19,10401 540. 0 197l0501 97010000 0o I 1 .700 0

1971001 101 -03 0 3004 0 .0 0

t9010700 0 .0 .0 .0 0

11910001 0 .0 .0 .

09770000 0 3 7 0 .0.04

19770100 0 ,0

197707101 e 1977*301 .0 7

19770.01 540. 3 197?0501 97001000 0 0 0 0.470 0

09174001 -13 0 3004 0 :.S0o 09777020 0 .0 .0 .0 0

09070400 0 .0 .0 .0 0

05730000 0 3 0 0 o00

09130000 0 1

097300100 7 .003

09730700 3 7

19730300 .0 7

09730400 540. 3

09730500 97030000 0 I 0 .059 I

097304001 13 0 3004 0 .0055

097)0070 0 .0 .0 .0 0

09030490 0 .0 .0 .0 0

I0700000 0 3 1 0 0.00

17010100 0 0

17004041 7 .070

0700•070 3oO

I07000.0 540.

07010901 700010000 0 1 0 0.98

I0700040 -03) 01014 0 0.50 0

12017010

12000000

I7070S00

07018700 12O2111

07070400 03704500

I0707800

178020701

103000070

.31.0000

13110800

01311000

.3'.030

13110100

I0118400

13000100

.1 . :1100

03000507

0300110361

03100040

03000403

03000700

13100090

50114000 05101000

05108001

05110010

05010301

15100040

05110040

15100050

I5110601 051107000

150001101

o0500000

2000,00

701001000

!0100151

701001700

70M00000

70 0 a 0400S

?0100451

0 .0 .0 .0 1

0 .0 .0 .0 1

0 3 0 0 8.00

0 t

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3 7

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0

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70.06

0 0 0

0 0 0

0 0 0 o)IlOOOO 0 0

037010000 0 0

0 0.00 0. 00 0.01767 0.

1 ., 7 0

0 1

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0.0 4

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0.0070

5

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1 00.70

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0.o

0.

* COPPER 40DS

73

C

* COPPEO COOLES

* COOt PO1R REDUCT0IO

70700000 POWER 504 0S 3.305 .4 70700000 .0.00 1.000 0.75 0.995 7.00 0.770 5.00 0.447

70700007 7.50 0.337 10,0. 0.737 07.5 0.045 05.0 0.125 70.0 0.043

70700003 75.00 0.047 30.00 0.007 50.00 0.060 75.08 0.055 700.8 0.055 * 87-PoSl PO@EO REDUCTION

70700Z00 POWER 504 0. 57.*13

70700701 0.00 0.000 0.00 0.SSz 7.00 8.469 5.00 0.407 70700707 100.00 0.704 05.00 0.052 70.00 0.004 75.08 0.007 700.00 0.017

0

570. . 0

011010000

0 0.40 00 0.0171

8L/,FCIN I

873. °7.7

3)00000.

1430000.

7OLdfCTN 7 793. 1008.

793. 0088.

5-57f1L

0 0 1 7.40 a

0 0 . 7.90 0 4. 9. 1

17 0. 0. 0

513. 9.45 673. 3.75

S 973, 50 0071. 7.30

3100000. 0?3o800. 3465000.

3713000. 1740000.

P.• INCONL4 600

100.9 0.017I 0.000007162 0. 0

740510. .s73.5 -0.747 0.

:LIQUID LEVEL IN D00N DC ANNULUS AND D000COM1 TO 8R004 *00IGo 0 LIQUID * 7CT OF LIQUID VOID

70701000 ao0m4 10 V00L1*

70701000 0. 0. .2940 !7740 1.0 0.549

70701000 080&R484 *VOLZI-3

?0701070 0. 0. 0.98 081.50 1.0 0.206 70700300 770P

70701300 0. ?90. 70200400 HOC-I

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20500000 LIOZIoZ OUNCT 1

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70501001 00007 021070000 911

70500200 L00070-3 FUNCTION 1. 0* 1

70500101 VolOF 001030000 007

20501100 LICLIVOC SU0 1. 0. 1

70509000 1.015 0.300 V0ID, 077010000

70504007 8.870 V080 0810080000

70504103 0.820 VOID0 071070000

7050400 0 0 020 7 07V000000

20504106 0.820 VOIDE 07000000

7050.107 .1446 0100 070040000

773. 3.10 70010408 0. C.TOLVI0 007 7050.009 0. CNTaLVAR 011 70500100 0.904 0000' 07101000 • LIQUID LEVEL IN UPPER PLiNU8 

000 50100 POPE

HEIGHT OF LIQUID - 7CT 07 LIQUID VOID 70707000 O4084401 *0OL$5-

0. 0. 70787000 0. 0. 0.050 0.823 0.316 0.08B

0. 0. 70770107 0.45 073)9 0.875 0.309 0.0 0.$57 Z05I2700 LIQ05?-0 FUNCTION 0. 0. 0

78507.I0 000.010000 070 2050"*00 LIOLEVUP 'U0 0. 0. 0 2050401 0. IOI00 051,100o0

05047202 1.0 CNIOLfIM 070 78509703 0.95? VOIDF 057070000

*L10U1' LEVEL I. COE

70S04300 LIOLCORE Su" 0.340 0. 1

7058300401 . *. VI:DF 009800800

70504303 I: V IDF 004070000

7050410) 0. vOID? 004030800

?050.304 1. .0o00 0090@0010

70:04105 0. o .1DO 009850000

70904)004 . vIOID 004064000

7050430 0, VOIDO 004078080

TOL./fCIN I I * COPPO

190.0

3.4i0*06
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.8

1985-10-22

z#5*4)00 I. vOIDE 0040800000

20004309 0. V0100 004090000

004300 to 00007 004I00000

*LIQUID LIML IN LOVER PfI.NUM Z0004400 Ll04(VLP SUR S l* 0. 20004400 0. 0.000 70007 03101*0011

00004402 0.300 VOIDF 3Z00OOO0

50004.03 0.171 vaIDO 33010000

*000 CLADDING limp $&WE UP

20000400 Os01 O CLIADT1P I MUm. I . 0. SEMP 40100010 ; R000 CLADDING INNER TEMP VOLI

00504010 11.0T11P9 RULI '. 0.. 200004 MY CEP 400000S .000 CLADODIN INNER fEMp VOLZ

2 006300 CLADTEMP3 "U! I I. 0*. 0

Z050630 M N|0EMP 403000 JO 00 0D CLADDING INNER 019P VOLT

Z O0S400 atCL 0"MP4 MUL I. 0. I

20600401 MYTIPP 404000)00 .00D CLADDING I4NER TI(P VOL.

00506500 CLADYEMPS WOJLO T. 0. l

00064001 II[ EP .05000)00 *Jos CLADDING INNER 1(1R VOLO

20006600 CLOOTENP6 KUL I. 0. I

Z0506600440 EMP 4060001 0 !0D0 CLADDING INNER 0(1P VOL6

00S06700 CLADI40 Y RUO.I 0. 0. Z0506700 000114 .0700000 000 CLADDING INNER limp *0L7

20506p00 CLAODT1,PO MOLl I . 0. 1

0506800000 MOiP 401000a,0 *RGO CLADDING INNER TEMP VOL@

00506900 CLADOIMPO NULt I . 0. I

506901 HI[71P 409000100 *-OD CLADDING INNER TEMP VOL*

00:00000 CLAOODEI NUL0 

0. 0. I 05000000 140[P0 410000104 *OOD CLADDING MIDDLE lImP VOLIO

* T41 RANSFER CO17 11CHAT 1 AT4IISUROACE 40P-FLUID TEMPI)

00004100 1 10COtfl OUR I 0. I

50:00101 0. M. 1M4IC 400000191

o0000000 ;oCOO2 OUK 0. 0. •0000901 0. I. NINOC .O0001011

S000400 .VCOEF3 SUM 0. 0.0 0000030) 0. 0. 140141 40)000604

0o000.00 14;1004 SUM I. 0. 1

z000901 0. IM IMTIC 404000101

Z0000000 .lCOE0 OUR I 0.

0000 0. I. 140r7 00O0010I

Z000400 n. 0C0. OU. I* 0. I

0S000401 0. 1 MOC 406000101

Z0000700 oTCOEFT ;U. I. 0. 1

Z0I00I0 1 0. I. MIMIC 407000101

000 00 14TCO(F SUR 0. 0SUN +0000001 0. I. NiNic 000000101

200000100 "OCO(F9 OUR I. 0.*

000001401 0. 0. OINOC .09000001 20,009o00 "COEIlO OUR . . 0.

2000001 0. M. 1IMIC 40000101

* LIQUID LEVEL CON|100 SYSTEM FOR DC ISI0 DY 0I0*0 ONL0 )

300000 LtVCIMVOL OMDPVOL

30a0101 I. I* 0. 0. 0. 0. 0. 0. 00

3000200 0

1000001 0. v.0F4 0. 4000000 LEOCrOJUN TMOPJUN

40s0100 400000 305000000 0 0 C"rfLVAR M01010000 0490.0

4001?01 -0.2 .0.0 0. 0.

Q0S0.0Z 0.0 0.0 0. 0.

20000400 L(VCOR OuR 0. 0. 0

21504901 6.340 -0. CNORLVAR 041

20100000 S3R-1LOSS SUR 1. 0.

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050000003 . 4 1401.AN0 330000100

000001.4 .0404: MIN04 S1000100 20500000 .07090 1401. 00100000

20900004 .29939 HT100 0270000100

20000000 .Z1943 140010A S?01000

z000s000 3.40070 1401. 101000100

0 000000 .40000 01.0 102000100

20000010 .43 46 A OIN: 211000100

0050011 sel 0441 NIRN4 010000100

20050010 .03700 013000100 20RNR 

20S00013 .,01. 1401.". ?1t000100

Z050 0is .343:3 140N4 1I0000*00

0 0 000 .334 14049 11 .Z00 Z00OSS001' 43 3 MTY1. 010000300 20000000 .300034 H4jNR 010000400

00505010 .0.234 M10NN 110000000

z0O00000 .01834 1 4RNR 710000140 00900000 000230 MIRED 710000700

200S0000 5o TMITLOS5 SU I. 0. 0

Z0100100 0. .02034 1470R 7000000000

z0•0010? .30330 Ty0R 0 20000100

20005003 .44063 mTRNR 730000100

20005104 .130Z a5 IRNO 40000100 20004190 .00490 14001. 040000200

20000St06 .66634 10RNR 7.0000300

0 00%joy .344012 1tR0 740000400

Z0000008 .00000 a 01RNR 70000100

Z0090109 .47000 14T1.0 40000100

20 05110 .4.9.0 14704 I. 000.00

2 0 0 5 .1 1 . 0 1 6 0 -I R M AR 6 4 0 00 0 z00

Z00001 .4121 14704 447000300

?05013 .?00@g TNIRM 910000100

00000513 .1444 1TA0. 910000100

0000 0114 .00000 1 ,0"0 10000000q

00000110 .49i4 147049 900000000 00000511 0.00 140614 3110000101

0090Sill 0.01 00M1R 311000)01

?0 0S0 0.03 0IRMA 311000301

00005119 0.20 .7-1. Im S.00000.

000000 .S0000 144INR 202000100

Z0o00000 %0-0 U "O 1. 4. 0

001400 0. .000 1 404•0 ,•0000100 00000000 .34190 147040 940001100

Z0 0S0 00 IIAL SUM NO 0. 0

200140•101 0. I 140CILVN 50

ZO0S030 Z00000303

?00000400

20000401

ZOSOS&O0

05050100

20000000

20060000

05050090

Z0505000

201006040

20050050

20050009

20000060D

20000100

20070000

2000S0901

200000000

Z0000090

20050090

20000900

20011000

20001001

20000000

Z0051001

20511004

200110007

200001000

•0000000

20SI0010

+0000011

20000101

20091141

Z0Sl0000

000I0101

Z001101?

•0011009

00011000

000011101

000II100

+0011103

2200-1100`0:

2osiio

01050S4,1

,05111?5

ZOSll900

?2 Oslll5 9:

I. Ih CN1RLVAA C1':LVAR 0052

S IR HTI N7 INT EGRAL 1. 0. 0 CNIRLV*0 00

00r91 -10SS INTEGRAL 1. 0. 0 147106. 150100000

M0Y-ROLOS OU•R 0 0. 0

0. .000 147N 01.40000100

.00 04TRNR 400000200 .100 NORNO 41.0000300

.150 1.T0N0 400000400

.Is0 HpRA4 40000000 .100 mIffNO 40000*600

.100 14701. t000010000

.100 14091. 400000900

.000 140940 400001000

COO-P09 'UNCTION 0.

I11( 0 000

BYPA SS-P0r FUNC TION 1.

1114 0 000

0. 0

0. 0

T0oTPOw SUN I. `* , 0. 1, CNORLVAO 07

0. CN.0LV949 00

AU X-HTLOS5 SUR I. 0. 0

0. .0900 141R. 310000100

.33000 4709R 320000101

.00090 147040 0000101 .. *10000 147040 101000101

.068Y4 10NR14 100010101

4.00037 0TRNR W50000101

.40000 1491. 1am 000100

.0914 3 1474R II1000I01

.14903 170N9 I12000001 .09)00 00940 003000001

.0,000 14001. 00A0001000

.4433) HyNR 710000101

.44:33 MTRNR I0000001

.443 1HI4N04 I0100101o

.3640 00040 7N00010401

.304106 14091. 710000401

.341.0 S 1401. 0100001

0U 3*AL05$ OUR 1. 0. 0 0.* .4,024 00049 7I0000101

.03377 14001. 700000101

.3)104 14001. 030000|00

.16021 1IR MA 7 400000 e

.31 3. 1.00 00010

.00301 M1R4 R 7.000031 ..•4079 14791. 700000401
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.9

1985-10-22

20511100

20413309

2041130

20511111

20511112 20511113

205S11114

20411111

20501111

20531116

2051103 20511119

205310020

2051 3700

20511201 2051 IZO?

20511300

2051 1301

20511302

20511303

.05500

.70'"'

: '.51T5)0

.40?53 .07900

.48048

.34038

.22449

.31830

.52574

.05500

.50000

* 30000

HT 47 HT:NN

HTRNR

MT04:

"TOMA

H70N3

010N0

TRONR

1.500O101

420000 101

'40000161

040000201

440000300

900000100

940000100

950000100

971000100

972000100

973000101

201000100

202000101

AUO-HTLOS SUw I. 0. 0

0. .37439 0TRNR 920000101

.41241 WT1NQ 960000100

TT-AUX-HTL SUN I. 0* 0

0. 1* CNTOLVAR 110 1: CNTALVAR III

I. CNTLVAR 112

* ll INITIAL . VALUES

0310200 3 7117300. 41.70

0320200 3 114560. 4o|*T7 0330200 3 7113300. 541.80

0S00200 2 7030120. e.10041

0130200 2 7040700. I.e

0720200 3 7041340. S40.:9 0130200 3 7005300. S41.10

0420200 3 7073500. 5400.0 0910200 3 10.2000. 401.?)

0920200 3 7002750o. 41..2 0040200 3 7045350. 54.0.5

09&0200 3 7020900. 53..15

0400200 3 7123710. $36.77 2000200 3 7112300. 5.1*03

2020200 3 ?104330. s4'.70 0041201 3 7072590. 550.04

0041200 2 70693400. 0.004214

0041203 2 ?0063|0. 0.02207

0041200 2 7043500. 0.039025

0041205 2 7099400. 0.054152 0041706 2 7056000. 0.0707040

004120? 2 7053950. 0.093220 0041200 2 7047590. 0..3705

0041209 2 7044010. 0.16701 0041210 2 1039500. 0.25524

0521201 2 1034070. 0.og4*3" 0201202 2 7002070. 0.79232

0111201 z 7002950. 0.009 2

01M1201 2 7002000. 0.52007

012120? 2 70013%0. 0.44125 0211201 2 7003220. 0.00077

0233202 2 7003440. 0.00030

0211203 3 7009040. 450.90 0. 0. 0. 3 0211204 3 7011500. 5$1.9' 4 0. 0. 0. 

00?3200 3 01030000. $41*3 0. 0. 0. 0 0743203 0640201 3 3 7M20000 1043530. 5o3.?5 0. 0. 0. 5 505.99 0. 0. 0. ) 0644202 3 0053200. 453.09 0. 0. 0.*

0641203 3 7043500. 55@.0Z 0. 0. 0. 3 0971201 3 7110000. 541.65 0. 0. 0. 3

* JUNCTION INITIAL VALUES

0041300 0 00:1301 1.191 030? 0. I 13.19 1.101 0. 2 0041302 1.699 1.637 0. 3 2004 5.019 0. 4 0040303 2.270 6.435 0. 2.52 7.534 0 4 0041304 2.842 0.305 0. 1 3.691 8.707 0. 0 0041305 4.251 9.297 0. 9

0521300 1

0421301 *.35 1.16 0. 1

0020300 0

0121301 -7.12 .746 0. I

0211300 0

021101 1!%.A 0. 0. 3

0711300 I 0710301 33.96 0. 0. 7 0703300 I

0711301 4.56 0. 0. 4

0401300 1

0041303 0.00 0. 0. 2

0971300 I

0071301 3.55 0. 0. ?

o•eCUANGE CARDS T. 07T CORE . PR(SSURE DROP ...

0 0010"0 3.710 0.0430 00 2 3 0520901 0030303 0.70 0.70 * 033030000 004000000 0,0000713 0,500 0.200 0000

$

0

9

30

2

2

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0I.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

4.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.10

1985-10-22

0000100

0000202

0000200

0000200

0000002

0000100

0000%00

000o20o0

0000000

INPUT T00 AO/LSPT00Z0 P2l-22 OPL11 00[00 2000020"? .. 07[000 $1Th 00 0 0

200 000 PO0(R MEAN COPE CHANNEL .(110A10 PI.IaNSNT

mu..

011 20. 00.

0.0 1.01-0 0.05 0000? S 100 100

0,. I.OE-6 0.? 0000? I so S0

02L0 0 1 N U2LL 0 0. L lint 0 Li 0UL2 u 0 0. 

TIME 0 a0 002. 0 0. L

0;)00000 aOLlI SGLVOL 02)0102 0. 2.000 0.01001 0. 0. 0. 0. 0.

0210100 0 00000O00. 2.

2200000 40020*20 0062.Ju.

2200002 2 0. 0. O.

2200000 1-00S. 00 ....

21 00 20 1 0 0 0 0 2 00 0 0 0 0 0 00 0 00 0 0 .0 0 0 0 1 0 . 0 . 0 0 0 0

::0102 2 0,000 0. 0.

1200000 W060020 *fi 000 2. 00.2 coo*.O00 111:10 "T"'Ll , 0.11,41 1-1. O.-ING III TRA&NSIENT

200002 0000503 000050? 0.0? 0.1288 2200.00 2.0 00.00

2270.00 .000 .000 .000 .12? .0906 .0003 .?00 .2)01 .1)01 2200.0? .000 .2000 .2000 2.00 .000? .2000

0000000 0(2.20' • OOOPOOO

000 0 N(LI(f T-DPVOL

001020 0.000)0 2. 0. 0. 0. 0. 0. 0. 00

0000?02 0. 2o00000. 2.0

1 llllllllll 0 A.ll I

;oloooo •(UIPI ImPUMP

0010020 00S010000 )0.000000 0.00000000

.0.01.0 0 1000. .0002 200

1 00.010 0. 0. 0. 0.

t000?0 I2..0 0. 0.A.00 

1020000 P0*0i POOP

1020202 0. 0.00o 0.0l020 0. 20.0 0.?0) 0

0000000 0|0200000 0.000000 0.00 0.00 0000

0102000 2 0.0 0IOFO o. *|

0020000 2 0.00 0. O.

I002032 0 0 0 -| 0 0 0 002000? 03.09. 0.000092 0.0O)O $0. 02.0 2. 2000. 0020003 0. 0. 0. 0. 0.

M 000 0O0OL0O0 PU"PK00000 00.. 00... a FR00. *0AT.*A00 G0002LI.0(0.

• O0Q00*KUVOAN0 S00 NAR 0fTYD(L. 0 I 0000 FPALL 0C1 NA0 0A00I0 IN2% 0ON02OLLERA!5. K2LLA. FIR 00 00L.OAA 00 K000D. 0002200 0 2

o 02010 0.00.2.202 0.00.2.200 0..8.700 0021100 0.00,2.030 2.00.2.000 00 02012000 0 0

0102222 0.00.0.00 0.00.0.00 0.Ig9.0.0

0022000 0.00.0.00 0.09.0.900 0.00.00*9 2.00.0.00

0 22000 I 0

2002200 0.0.*0.0 0 0.0-0.1560 0.Sl.-0.05 0.10.0.40

0022000 1.00.12.0

2011.01 0.0.-1.10 0.5.0.00 0.00.0.31 2.00.1.00 0022000 2

00000]S02 .00.1.00 -0.90.0.00 .0.00.0.~~ -9.00.0.39 0022000 0.00.2.20

?002000 I 0

0022002 -2.020.?00 -070.120015 .040.2 .00 0.30.0.90

00220002 0.00.0.0? 002t700 0 0

0022002 -2.00.0.12• .0.00.0.00 .000.60.009 .0.0.6.h90 0il02 -0.0,..9 -0..2.20 -0.20.0.99 0.00.0.00

0022000 0

0020002 -1.0.04.1 2 000?.0. -0.09.?.)? 0.01*.0.0

2002200 0.02.2.00 0.00.2.0S 200 P000( 00 . 2LI 00LIER 2IAL(0

?01)000 0

0020022 0.0.0.0 0.2.0.0 o .0.20.0.00 0.06.0.0 0.0.0.0 0..0.9o

020100? 0.0.0.90 0.0,0.0 0.0.0.0 0,90.0,A 2.0..00 0020202 0

0021102 0.0.0.0 0.2.0.0 o20*%.o*0 0.0,0.0.8 0.0.0.4 0.9.0.90

0220200 0...0.9 .0.o 0.9.0.0 0.00.0.1 1.0.0.0

;000400 - 2 ?002202 0.0.0.0 0.2.0.00 0.0.2.09 0.0.2.00 0.7.2.02 0.90.00*9 2.0.2.0

0201400 I 0 •012001 0.0.0.0 0.21.-0.00 0.0.0.0 0.0.0.2 0*.0.0.0 0.0.0.00

0020000 0.9,0.00 1.0...0

0020002 *2.0.-I.10 -0.9.-I .00 .0.0.-I.?? -O*.*2.-0. *O.0.-?2*9

?002020 .0.0.-*?.91 -0.0.*?.0 -0.l0.-I.09 .0.211-0* 0.0.0.0

?002.02 -I.0.'1.16 -0.9.-a. 20 *O.0.0O. -0. 2.0.)l *0.0.-0.110

2010.01 *0.-0.00 "n.35.0.0 -0.o.0.00 -0.2.0.00 0.010.12 1 2.0 P.0S( OIFF000

9c0 rap PUMP 2O00U0 o. SINGLE 1."1W. ."IC" -(000 IN&•I FULLY OffRADID 1 I~ 001t 

0020900 0 2

00i20o0 0.00.0.0. 0.09.0.01 0.19.0.09 0.01 0.20.0.90 0.%9.0.96? 0.00.0.9 h.00.1.00

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?010100 1-I ?01, % 01 -i.00,1. 1 -A,A II oA * . f? -011 011 *19s

0021020 *0.,00.1,9 -0.00.2.29

020S00 0

0020002 -2.00.3.11 -0.19.11.0 0020000 -0.21,.2.0 0.00,.2.0 A,2.z 2( ouP 

0012100 S00 0202020 0.00 200.02 0.00

?00200? 0.00 000.09 0.02

?010103 IS.00 ?9.39 20.00

0000000 30.00 07.09 40.00

002020 200.0 209.57

"0.0,0.90 0.00.0.09

-0.09.0.00 -0.02.?.00

209.00

220.70 20.00

00.09 03.00

97.02

09.00

7000000 P0M00 Po0'

0000202 0. 0.000 0.00.00 0. 12.0 0.000 0 2000000 090020000 0.019 0.00 0.00 00c0 0002009 090000000 0.0000)00 0.00 0.00 0000 ?00000 ) 0.200010I00 0s2.0B 10:101 .... 1.25O . 6

M0u0002 2 2.SS 0. 0.

0000 0 2 .00z 0. 0

20000 0 0 -I -2 0 0 0

1030?00 301.69 0.0SS00, 0.026 00. I)2. 2.

t00?000 0. 0. 0. 0. 0.

00220110 2

0021101 0.0 1.116 0.? 0.0 '.I0' .1200 2002200 0.6 1.100 0.0 .000 20 h000 02 0 00 2 2

0002001 0.0 0.21 1.0 2.00

0002302 0.0 -0.000 0.? -0. 000 0.. -0.200 0.0 -0.000

00021•00 0.0 0.200 0.0 0.909 2.0 2.000

?000200 0 2 ?000201 0.0 -0.01 0.? -0.02 0.0 0.0'

002000 . 0.00 0.0 0.00 1.0 2.00

?001000 2 0 0002002 -2.00.0.00 -0.90,2.01 -06.00.2.0 -0.00,2.20

0011020 0.00,1.114

?001000 I 0 0100200 -2h00.0.00 -.0.9,.005 -0.01.21.00 -0. 20.0.9)

0002000 0.00.0.7p

?002000 0 I 00200210 -. 00. 2.02 -0.00,.0.0 -0.00.0.10 -0.00.2 .00

0012100 -0.01.I.. -0.2,I1 .0.10.0.99 0.00.0.90

1002000 0 0

1:1210oi -2.00.3.02 -.. 0..o -0.99,.1. -o.9.:.o00 0002000 -0*?.02.2. 0.00.2.00

2 0002002 o )oo 0.0 o 0.00 .7 0.2 . 0.20 0.? 0.00 0.2 0.00 0.0 0.90 0.0 0.00

0000000 0.0 0.02 0.0 0.90 0.0 0.00 0.0 0.00 2. 0.00

2002101 0.0 0.00 0.2 0.20 0.0 0.10 0.2 0.00 0.. u.2. 0.0 0.00

"000020 0.0 0.00 0.0 0.00 0.0 0.90 0.90.90 2.0 2.00

2102600 0

00002012 .0.0 2.0.

2000.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix A.11

1985-10-22

:5TEAK RELIEF FLOW 9001L

20I09300 64OP "0LT7 2 0, 0

10009302 6.O0 *13010000 P 013010000

20509400 $0110 p09(66 |. 0. 0 20 50 940 2 C NT RL . ': 09 3 0; .

20209300 ORMAR0A

20209301 0. 0. 0.4 0. 2.0 0. 20209302 Ib.0 1: ?.30 0- 1;20- 0.

20209303 12.65 1.

20509000 T7R(00 IOIPOLAY 1. 0. 0 O09S0 b

20509600 "0-10100K" SU. 1. 0. 0

2050900 I. 0. I T 0 2050960z -_. CNTRLVA7 095

20509700 TRPTES? TA|PuNIT 2. 0. 0 20509701 504

20I09000 001o( .1UI 1. 0. 0

20509602 CNTRLVIR 096

2050900Z CHIP VAR 09?

Z0509900 VL0IRI0 (06C0I0O 2.03401-4 0.

20?09901 CNTPLV.. 0a9 093

20S20006 ".,SLO: 9ULT 0.661& 0. 0 !0SI900 (I C IRL V 099 CNTALVAO 094

;0500100 "ASSOIFFI DE(L(E ZOS.00+0 '"10 IYOILI OILFTl ?0500200 IV000O4L2 001(00

20500100 9 FSD|FP? DfLFIO

20s00%00 1,45[GRAt? 0(L(2

10500600 V2L0IF( 2 DELETE

2050000 LIVCIRVOiL .11(0 4050000 L00C00JUN 0ftf(0

20564900 L0VCIO PaLr00

1..?

0

4-

FLUID DENSITY. CORE BOTTOM IRHO 0401) CASE A

FLUID DENSITY. CORE BOTTOM (RHO 0401) CASE B PLUID DENSITY. CORE BOTTOM (RHO 0401) CASE C

FLUID DENSitY. CORE BOTTOM (R.O 0401) CASE 0

Plot B. 1

-1

11-1

In

co

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In

p)

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o __ _ _ _ __ _

0 ________

0

0 _______ _______ _______ _______ _______

o

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0N

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0

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W.-

-10 o10 20 30 40

T IME (S)

50 60 70 so 90

(90

A

+

X

DIFF. PRESSJRE. CORE INLET RES T

RICTION (OPT 4) - EXPERIMENT

DIFF *RESSURE. CORE INLET RESRICTTO' IP 330) - P 40) CAS 0IFF PRESSURE. CORE INLET RESTRICTION (P 3301 - P 40)) CAS

0IFF PRESSURE. CORE INLET RESTRICTION (P 3301 - p 40)) CAS

DIFF PRESSURE. CORE INLET RESTRICTION (P 330) - 0 401) CAS

Plot B. 2

I:z~

'-4

0

'-.4

U)

DC

fTIME (S)
0

A

+

ELECTRIC POWER. CORE (CALCULATED),- EXPERIMENT CORE HEATING POWER (CNTRLVAR 5?) CASE A HEAT LOSS FROM PASSIVES (CNTRLVAR 53) CASE A HEAT LOSS FROM PASSIVES (CNTRLVAR 53' CASE B HEAT LOSS FROM PASSIVES (CNTRLVAR 53) CASE C

Plot B.3

c..J

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04

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090

A

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x

MEAN CLAD TEMP.. LEVEL 1 IT019 7206 T211 7246) - EXPERIMENT MEAN CLAD TEMPERATURE. LEVEL I (HTTEMP 401000105) CASE A

MEAN CLAD TEMPERATURE. LEVEL I (HTTEMP 401000105) CASE 8

MEAN CLAD TE"PERATURE. LEVEL I (HTTEMP 401000=05) CASE C MEAN CLAD TEMPERATURE. LEVEL I (HTTEMP 4010001051 CASE 0

Plot B.4

'-4

En

pEn

Az

TIME (S)
Q

4.

x

MEAN CLAD TEMP.. LEVEL 3 (TiO 1183 t243 T248) - EXPERIMENT MEAN CLAD TEMPERATURE. LEVEL 3 (ITTETP 403000105) CASE A

MEAN CLAD TEMPERATURE. LEVEL 3 HTVIEMP 4030001051 CASE B

MEAN CLAD TEMPERATURE. LEVEL 3 (HTTEMP 4030001053 CASE..C

MEAN CLAD TEMPERATURE. LEVEL 3 [HTTEMP 403000105) CASE D

Plot B. 5

co3

tlJ

N

I

0

In

La)

co

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0

aQw

c,,

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0

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aTIME (S)

0 MEAN CLAD TEMP.. LEVEL 5 CT202 T22? T232 T23? T232) - EXPER 0 MEAN CLAD TEMPERATURE. LEVEL 5 (HTTEMP 404000105) CASE A A MEAN CLAD TEMPERATURE. LEVEL 5 (HTTEMP 404000105; CASE B

+ MEAN CLAD TEMPERATURE. LEVEL 5 (HTTEMP 404000105) CASE C

X MEAN CLAD TEMPERATURE. LEVEL 5 (HTTEMP 404000105) CASE 0

Plot B. 6

H

I-I

1-4

Z:

T IME (S)
0

+

x

MIEAN CLAD TEMP.. LEVEL 9 (T102 TW TIGF T172 Tl8? T197 T27 MEAN CLAD TEMPERATURE. LEVEL 9 (HTTEEP 406000105) CASE A MEAN CLAD TEMPERATURE. LEVEL 9 (HTTEMP 406000105) CASE B MEAN CLAD TEMPERATURE. LEVEL 9 (HTTEMP 4060001051 CASE C MEAN CLAD TEMPERATURE. LEVEL 9 IMTTEMP 406000105- CASE D

Plot B. 7

Lj4

co Lu

04

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URE. LEVEL 15 MEAN CLAD TEMPERATURE. LEVEL IS MEAN CLAD TEMPERATURE. LEVEL 15 MEAN CLAD TEMPERA T

URE. LEVEL 15

TigO T27S) - EXPERIMENT (HTTEMP 410000105) CASE A (MTTEMP 410000105) CASE 9 IHTTEMP 410000105' CASE C (HTTEMP 4100001053 CASE D

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FLUID TEMPERATURE. CORE OUTLET ITEMPF 501) CASE 8

FLUID TEMPERATURE. CORE OUTLET VTEMPF Sol0) CASE C

FLUID TEMPERATURE. CORE OUTLET (TEMPF 51011 CASE D

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FLUID DENSITY. 4ESSEL BOTTOM (RHO 31013 CASE B FLUID OENSI|T. iESSEL BOTTOM !RHO 31011 CASE C.

FLUID DENSITY. IESSEL BOTTOM (RHO 31011 CASE D

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DIFF. PRESSURE. DOWNCOMER (OPT 27 - • OPT 30) - EXPERI D01F PRESSURE. DOWNCOMER (FROM P 7103 - D 7201) CASE A

DIFF PRESSURE. DOWNCOMER (FROM P 7(03 - 7 '2011 CASE B

91FF PRESSURE. DOWNCOMER (FROM P 7103 - 0 7201) CASE C

DIFF PRESSURE. OOWNCOMER 'FROM P 7103 - P 72013 CASE D

Plot B. 14

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D1FF. PRESSURE. LOWER PLENUM (OPT 2 - OPT 3 - OPT t) - EXPE DIFF PRESSURE. LOWER PLENUM (FROM P 3101 - * 3301) CASE A D0FF PRESSURE. LOWER PLENUM (FROM P 3101 - P 33ail CASE B D0FF PRESSURE. LOWER PLENUM (FROM P 3101 - P 33011 CASE C D0FF PRESSURE. LOWER PLENUM (FROM 0 3(01 - P 33311 CASE D

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A D0FF PRESSURE. UPPER PLENUM (FROM P 5101 - P 52011 CASE 9 PlotB._16 + 0IFF PRESSURE. UPPER PLENUM (FROM P 5)O - P 5201) CASE C x 0IFF PRESSURE. UPPER PLENUM (FROM P 5 0) - P 52011 CASE 0

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DIFF PRESSURE. StEAM SEPARATOR ORIMICE (P 5201 - P 5202) C

D01F ORESSURE. STEAM SEPARATCR 0RICICE tP 5201 - P 5202) C DICF PRESSURE. STEAM SEPARATOR ORICICE (P 5201 - P 3202) C

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CLUID TEMPERTURE. UPPER PLENUM (IEMPF 5201) CASE 8 rLUID tEMPERTURE. UPPER PLENUM (TEMPF 5201) CASE C CLUID TEMPERTURE. JPPER PLENUM (CEMPF 5201' CASE 0

Plot B. 18

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FLUID TEMPERATURE. DOWN COMER BOTTOM (TE 31) - EXPERIMENT FLUID TEMPERATURE. 004NCOMER BOTTOM (tEMPC 7108, CASE A FLUID TEMPERATURE. 9OWNCOMER BOTTOM !TEMPF 7108) CASE B FLUID TEMPERATURE. OOWNrOMER BOTTOM (TEMPr '1081 CASE C FLUID TEMPERATURE. OOdNCOMER BOTTOM ITEMPr TIM8 CASE 0

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ORESSURE LOWER PLENUM 'P 3101, CASE 9 *RESSURE LOWER PLENUM (P 3101 CASE C PRESSURE LOWER PLENUM U P 3101; CASE D

Plot B.20

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0,. PRESSURE. UPPER PLENUM (PT 4) - EXPERIMENT PRESSURE. LIPPER PLENUM (P 52011 CASE A PRESSURE. UPPER PLENUM (P 52011 CASE B PRESS"RE. UPPER PLENUM (P 52011 CASE C

PRESSURE. UPPER PLENUM (P 52011 CASE 0

Plot B.21

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0 MASS FLOW RATE. BYPASS (CALCULATED) - EXPERIMENT 0 MASS FLOW RATE. BYPASS (MFLOWJ 117) CASE A a MASS FLOW RATE. BYPASS (MFLOWJ I]7) CASE B

+ MASS FLOW RATE. BYPASS (MFLOJ 117? CASE C

x MASS FLOW RATE. BYPASS IMFLOWJ 11?) CASE 0

Plot B.22

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TIME (S)

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1 MASS FLOW RATE. l..,. UMP (CALCULATEO) - EXPER1MENT 0 MASS FLOW RATE. I.L. PUMP UtMFLOWJ 20102) CASE A A MASS FLOW RATE. IL. PUMP (MFLOWJ 20102) CASE B + MASS FLOW RATE, I.L. PUMP (MFLOWJ 20102) CASE C X MASS FLOW RATE. I.L. PUMP (MFLOWJ 20102) CASE D

Plot B. 23

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x MASS CLOW RATE. B.L. PUMP (MFLOWJ 20202) CASE D

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MASS FLOW RATE. B..6. fESSEL PILET, tPFLOWJ 9702) . CASE A.

MASS FLOW RATE. 9.L. VESSEL INLET tM'LOWJ 9702) .CASE B9 MASS FLOW RATE. B.L. VESSEL INLET (MFLCWJ 9702) CASE C,

MASS FLOW RATE. BL. VESSEL INLET (MFLOWJ 9702) CASE 0

Plot B.25

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0 TOTAL MASS. IN SYSTEM CASE B

A TOTAL MASS. i4 SYSTEM CASE C

+ TOTAL MASS. i1 STSTEM CASE D

Plot B.26

TIME (S)
a

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MASS CLOW RATE. STEAM RELIEF (CALCULATED) - EXPERIMENT MASS CLOW RATE. STEAM RELIEF IMFLOWJ 404) CASE A MASS CLOW RATE. STEAM RELIEF (MFOWJ 4043 CASE 9 MASS CLOW RATE. STEAM RELIEF (MFLOWJ 404) CASE C MASS FLOW RATE. STEAM RELIEF (MFLOWJ 404) CASE 0

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FLUID DENSITY. BREAK (RHO 9601) CASE Q Plot B.28

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0 MASS MASS VW ORATE. RATE. BREK BREAK FROM T2 IRVENTORT (CALCULATED) - EXPE 0 MASS C W RATE. BREAK (MFR2OWJ (MFLOWJ IS2) (521 CASE CASE AB

+ MASS F W RA E. 8REAK (MFLOWJ iS2) CASE C x MASS FtLOW RATE. BREAK (MFLOWJ 152) CASE D

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Plot B.30

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T IME (S) SO 60 80 90
FLUID TEMPERATURE. BREAK INLET (TE 34) - EXPERIMENT " FLUID TEMPERTURE. OREAK INLET (TEMPF 9601) CASE A £ FLUID TEMPERTURE. BREAK INLET IIEMP1F 910)) CASE B * FLUID TEMPERTURE. BAEAK 1.LE. 'IEMPF 960 1 CASE C x FLUID TE"PERIURE. BREAK INLET (TEMPF 9601) CASE D

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PRESSURE. BREAK INLET (Pt 61 - EXPERIMENT PRESSURE. 9REAK INLET fP 9603) CASE 4

PRESSURE. BREAK INLET (P 9601) CASE B PRESSURE. SREAK INLET (P 9601) CASE C

PRESSURE. BREAK 1ILET (P 9601) CASE 0

Plot B.33

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0 CPUTI ME CASE 6

+ CPUTI.¶E CASE C Plot B.34

CP MECAE , 

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T IME (S) so 60 70 so 90
13 MASS ERROR CASE A a KASS ERROR CASE 8 A MASS ERROR CASE C

+ MASS ERROR CASE D

Plot B.35

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T IME (S)
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix c.1

1985-10-22

Calculation to experiment data uncertainty

Case A

cOrrf CALCULATION.T0-F0PPICNr•T OATh UNCC(RY6fV~t ANALYSIS FOR pAN/jCAAP.

FIRST LINE I !:Frr Nrfa flCT"CE" CALCULATED &Ni* lAVERA0202 EXPERImEkTAL QATA AT EN0 OF Tf INTEkVAL

SFCONn LINOE - OIFFrRF C" OVEA 0.4 INTOkVAL ?T..R LINE I .Fah StC'. 0A OVE TH NICAVAL 1NULT mEAN SQUAPE OF ThE O2FFERFNCti

- rOf - - -.. TI-F |hTfwvAL -.---..

CALC. L.AI0 (5•. 0.^ - - 12.00 - 1o*00 - 20.00 - 30.00 - 4S.00 - 60.00 75.00 ------------ .. .. .. . .. .. .. ... ** ------.. .. :.24.00... . . . . . .* :- .. *-.---. ...... ...--.. .

P I2 - P 3 -. A3(*al .'32r-71 .t0.0-UI .135C-01 -. 301E-01 -.622E-01 -.1Z7E-01 -.16S

-. 409F::i .:664-'0 .,b3E-01 -. %'IO-02 -. 2411:-: -. :S08-I0 -. 3Sar-01 -. 21E-01

Q- .oeo-oG b•1- 1 et01 -01 31[-01 .5tC-01 *2315 .EE-24OE

P ?A - 114 -. ?e1[-1 .A0ok-01 ..3•t-O2 .36ME-01 -. 129E-01 -. 330E-01 .1191-41 -. 866E-01

. ?3nE-:l .40hf-02 .he.o-0:l :2037C-0 -.067C-0? -:24:C:-1: -.250C-02 -:4 S0C.4 o30E-nE .51.[-0| *0JY-0) A232E-01 .141C-01 *240C-01: *226C°O .585[-0E

P 1 - P l -. 3.0(-..o .6-b-01 .183E-01 .372E-01 -. 650E-02 -. 546E-01 .ToO(-02 -. 102'

.2 15 .o5bC-OI .197C-01 .3491-0? :23:E-01 -:296E-01 -:19:0C -. SI IE-0 t

,3231-01 .71.-01 o 300C-01 .24CC-O1 .328EI 3 0 ,27801 .644CE01

P04, - -.%Is 1.41 2.20 .217 ,7A6 .342 .461 .S31

A2QF.?~-01 Ž.36 ?.03 2.49 .981 .839 .590 4.27 .113 2.b1 2.76 1.55 1.07 0.I1 .007

PDLA - e LP °4'A .. 19 .J36 .l?1 .491 2.26 .970 .251

.07 .'22 .:51 .262 .347 1.67 1.65 .726

.'30 .423 .*53 .282 .382 1.79 1.70 .76,

POCS - 0 CO .0.97 -*.Se -.IS. 3.31 -5.0? -7.97 -1.20 .643

06 -5.61 -**5? .943 -1.00 -7.2' -4.31 -,35T7-01

5.42 4.47 0.76 3.25 7.38 4.46 .743

POL'A - 0 UP -. 4(.A -. 794 -. 496 -. 469 -. 446 .496 -. 3330-01 0.SOIC-00 -6A5 -. N52 -. bb4 -. 571 -. 477 .ST2 .11I -. 413E-01

913 .461 :597 :594 .499 .614 .183 .46S[-01

PDAs - t DC -.2!4 -&..s -1.0. .964 1.94 S.23 .92( .183

-. 737 --. 49 -3.02 -,sob 2.43 3.33 3.21 ,119C-01 2:9.4% j, .952 2.58 3.58 '.52 .259

POSA - E. 56 -1.04 -1.,0 -1.00 -. 549 -. 736 -. 282 -. 172 -. 167 -0.10 -1.1 -l -800 -. 972 .5240-01 -. 369 -. 388

2.A 1.16 1,2( :8$N i.01 .332 .384 .42

MF15 - At-02 -.2071-nO .114.Ž0 .202 -.049 -. 342 -.42&E-01 .44CC-01 -. 136 .42OC-OC E:32 .1'' .1.3 -. 349 -M28h .723E-02 • I3 .93*0-1 2.2 .252 :217 .3TS .223 .483E-0

-rA - As03 -. ?.. .269q-03 .333 -. 64? .520 .84. .680 .74s

-.~39 -. 2'. .3:4 -. 775 -. 404 .33? .37. .404 •.:11 .144 *i! 2.03 0.06 .6%0 .4S• *490

.Fu - .4 7.. -. 373 -. 54u -. 654 -.340 -. %SSE-01 -. 339 -.62?

-. 410 6 -. 24 -. 40 .229 -. 2S -. *z. -.783

. 44 .410 .360 t700 .5:2 .352 .550 .801

.F. . 0607 .705E-01 .73VE-01 .3tst-0O .20DE-02 .7I5-02 .3450-0Z .882EC02 -. *40Z-02

• 931C-o1 .7120-01 .4'C-01 .3220-02 .108C-01 .4830-0Z .S30E-0Z .3340-02

2160 .7160-01 .152E-00 .324E-01 1220-E01 ,641E02 *8520-02 .719E-02

.F. .410 -. 23? -. 371 -. 241 1.41 .6S9 1.17 .840 .574

.231 -. 363 -. 510 .628 1.38 .894 .852 .:72 •.567 .3w. .•33 2,|4 0.52 .73. .690 .933

rf0 Z. 3 -7.24 0.S0 -2.28 -1.47 -. 1401-01 -.619 -.950E-02 -. s18

• .31 -.179 .560E-01 -1.02 -. 893 -.320 -.2000-*1 -.534E-01 7.30 1.1. .bb7 1.36 1.10 .410 .19S .178

T0L' - T 3 ?.42 2.91 5.53 3.85 3.65 .600 -2.93 -11.6 I*•5 3:16 3.71 5.97 3.40 0.37 -0.79 -4.25

?.00 3.39 3.4b 6.07 3.41 1.99 089 6.78

TFA - T 14 .2SO -. 690 .750 1.54 .530 .370 -4.18 -12.8 -.4107 -Al .28? 1.07 1.11 1.36 2.25 -1.73 -. 49

.750 .ý80 1.32 1.18 1.76 1.34 2.40 0.90

TFr. .T 15 .Sq0 2.4? 1.-1 1.71 1.23 .820 -6.66 -16.3

1.26 1.70 0.75 P.s4 0.20 1.15 -3.02 -02.7

1.30 1.77 1.67 1.27 1.23 1.07 3.12 12.0

TF0? - T 31 !.f3 *.14 -.349 -1.69 -1.93 -2.61 -1.00 -4.73

1.07 4.42 3.40 -2.4' -1.99 -?.36 2.,6 -3.29 1.!' 6.80 4.50 0.72 2.02 2.38 2.s3 3.42

TF-1 - T 34 .960 ?.31 1.35 -. 700E-01 -1.25 -2.01 -1.63 -3.96

q 2.9 2.31 .31? -0.27 -1.91 -1.94 -2.72

2.O 2.3' 2.34 .546 2.36 1.92 1.96 2.89
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix C.2

1985-10-22

... TIME 1T8RVAL - - - -

CALC. EXP. 0.0 " 6.0PD - 12.00 ..... °............. .. .... ......-....... ..... - 18.00 - 24.00 - 30.00 - 4S.00 - 60.10 - 75.00

.4718 - Ic I .4.4n1

myl-A TC 3 .10

4A.

14718 - TC12 1.10

*.301

1.3014

m~s- TC15 1.44

-:I (.8 -

-2.50

-1:43

?.S6 2.00

-3.73

3.80

-1.20

-1: IQ1

1.20

.. 70

1.00

.410 .574

. 640

-35.1

-34 9

34.0

-. 43SE-01 -. 8030-01

-1.84

-?M*

2.1.0

2.11

-L.Ou -2.23

-2.23

2.24

-1.4Z

1.60

.450

.344

.444

1.00

-34.0

34.1

-. 145E-01 -. 3840-01

.406t.-0

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2.19

1.7'

1.480

1.880

-1.7?

.217

.372

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-35.

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-. ,401-S3

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0.

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-. 194;:03

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-31,4

31.4

-Sq,8 -S6.6

54.6

-26.0 -33.4

33.8

-43.6

-41.2

41.2

-50.6

-. 1691-01 ".1190-01

.122E-01
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix C.3

1985-10-22

Case B

C071 CALCU'LA7On .70*16!p1*4?• 04Th UNC1'?A3•17 h'ILVSOS FOR NRC.,ICAAP.

FR1ST Li"e t oirrfpEkr 8 EE EN CALCULAIIED, D (AVERAOID| EXPER|NENTAL DATA AT END Of HME INTERVAL

S.CONO Li" e 4 DIAN Eoll," 0VEP91.O TM, 21T14VAL

t1060 LINE I -(AN .[00 0GVE1 TMH INTERVAL '603T NEAN SOUARE OF TME 0IFFEPENCE1

- ennts - - - - TINE INTERVAL ----.--

CAL'. 1'". O.f " 4.000 - 12.00 c1o00 - 24.00 3 0 45.0 ! 60.to - 75.00 .

I' - ' -.P'Of-nl -. I"-.e -. 3 -. 749E-01 -. 142 -. ?51 -. 360 -. 619 1.P'.1:- -. %;?1-OI -.*231-03 -. 100 -Z130 .203 -. 273 .476

._3'1-o1 .•O41-O0 .7531-0( !132 .103 .201 *374 .480

0 ? . -. EI!E-o .164E-01 -.4b41-01 -.460E-01 -. 17' -. 21A -. 333 -. 539

-.'22-ft1 -. 1051-01 -. 3011-02 -. ?071-01 -:103 ".173 -. 24A *457

.4 911.ni .?43C-03 .534E-01 .7451-01 .106 :ITS *z24 .A61

P w - P 4 -. 460E1.A -. 274E-01 -. lb -. S27E-01 -. 11? -. 24S -. 343 -. 550 .210 -. 6E5E-01 -. 4791-01 -. 7641-01 -. 111 -. F;' *-25S6 -. 66 .?74 .7141-00 .6541-O1 .813D-01 .115 .1:7 °258 .6'2

P0.- - 1 4 .?.7A .060 2.41 -1.66 I1S0 .424E-01 .304 -. 9681-03

-1.34 -1.3k 1.75 1.64 .M?1 :413 .794 .159 9.5. 173 l*eO2.41 .903 .SO 1 16 .600

00L - 0 LP .*"3 .41S .291 -. 131 .292 .ZZS *4001-i -. 709c-03

. 0 !1 **3Z .;46E-01 .662E-01 -. 301 .210 -. 268[-01

.47F .419 .465 :1'7 .254 .575 .219 1:447-E0

0nf- - 0 CO -o.20 -11.3 -5.-7 .640E-01 -5.08 -9.23 -2.23 .321

-7.? -9.95 -;0:. 3.813 -3.61 "7.S -6:23 -*.00

8.16 9.94 10.4 2.97 41 3 7.85 4.47 .876

PoJo - 0 UP -. 714 -1.25 -1.19 -1.06 -. 245 .6091-Ol -. 369E-41 -. 724-0ol

-.79T -.99S -0.33 -0.03 -,.39 31,1 -. 230161 -. 5091-01 .987 3.0 O0.33 1.33 1.53 *342 .581[e1 .5366-S 3

P". -. Cc -. *61 .654 -. 108E-01 1.96 6.9S 6.63 .917 .165

-. 013 1.1q -. 210 .464 5.23 6.59 4.00 .250 ;.*A 1.37 5,02 .S"3 S.56 6.64 4.30 ,297

P.S. - D ' 6 -1.54 -1.64 -1.47 -. 94b -1.08 -. SS -. 384 -.353

-. IS -0.52 -16 -1.4 -. 63F -. 472 .493 l. 0 9 1.53 1*N 1.07 1.91 .6?3 .6T3 ,508

.F1. - XO? -. 704.9-1 .5S3F-0l .352 .044 -. 8971-01 -. 374 -. 4361C.0 .6771-00

- 246 -. 107-0-2 7 -0 7 .8741-01 -3s9 -. 197 .2661-00

.285 .3SE -01 .064511- .164 .19 .33S .36s .8351-01

-V7ý- t.03 -. 646C.01 S571E-01 -. 486E-01 .374 .544 .*06 .46S .ISO -. 229 -. ?2?1-00 .460 -].26 .268 .4291-O3 .346 .266

.20. .933-001 .523 1:.%2 1.22 .684 *Sq, .313

X- .0 -. 231 -. 189 -.674 -. 494 -. 216 .110M-01 -. S26 -. 829

-. 229 ",1'? -Sol .644 -.2ig ".247 -.497 -. 858 .267 ,192 .596 .710 *318 .353 .596 .871

- 4494 0407 .705E-01 .739F-01 163c-01 .601E-OZ -. 862E-0Z -. 2SI-01 -. 462E-01 -. 728E-01

.92•1-0l .?7ZE-00 .4951-01 .1686-01 -. SS1-02 -. 176E-01 -. 304E:11 -. 5971-01

.210 .7161-00 .7371-01 .176E-01 .09E-02 .186E-01 .30 1R 1 .60S5-01

-F.4 - 1610 -1.11 -1.22 -. 281 .98? -. 6571-01 1.16 .as? .694

-.!7A -0.23 -1.27 ,773 .24T ,603 .936 .95s .839 1.?3 1.36 .:98 .507 .723 .956 .965

. x- 3h -1.02 2.53 -1.17 -1.26 .174 -.470 -.?29 -.42T

2.60 .?0. -1.20 -:624 -*III -.277C-41 -. 233

".63 1.. 1.02 1.29 s80? .284 .190 .26,

TFI© - T 3 2.44 2.90 7.98 2.17 1.98 -3.76 -9.73 -t3.'

2.96 3.17 5.28 5.8:4 .02 ".933 -5.97 -15.6 ,:00 3.40 5.52 6.26 2.05 2.03 6.19 16.1

Tr20 - T 14 -. 300 -1.32 -. T30 .440 -. 920 -2.60 -11.0 -24.7

-. 25? -. 248 .18S -. 375E-02 .7331-02 -1.02 -5.P7 -17.9

.920 .561 .671 .470 1.09 1.26 6.4S 18.3

Tr4p - T 15 1.01 1.81 -. 900E-01 .710 -. 230 -2.17 -13.4 -26.1

0.20 1.37 .1M ,s161 -. 166 -1.5S -7.24 -21. l.40 1.b2 .463 *40a .36 l386 17 7. 21.5

TF14 - T 31 P.22 A.06 -1.76 -2.73 -3.58 -5.61 -7.8) "16.5

T.17 7.63 2.44 -2.72 -3.36 -4.62 -6.60 -12.7 1.'3 7.02 4*4b 2.74 3.40 4.66 6.67 12.9

TF-A - 7 34 1.05 2.R7 .420 -3.59 -2.99 -5.06 -B.56 "1S*9

.40 1.59 2.33 -. 635 -2.60 -'.19 -6.19 -12.3

;.of0 1.66 2.46 1.02 2.85 46,2 6.26 12.5
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix C.4

1985-10-22

- *OrlF % - - - - - r3.E IN.TERVAL - - - -

C- L-- E!b'. - O - - -. 1".O * -.. -2.00 -4.00 0- -- -5.00 - 60.00 --. - 00

..73' - T'I

-P,.1 3

A 14

"0?' - Ir I 3 .44 ~*9..

? * 4

-3..'

2.0'

2.07

-2.73

-3.52

3.56

-: .3q

1:*32

-4.9

-Tl3.73

2.43

.660

3 45

1.58

-3.28

-2.93

2.96

-2147 -1.7.

3.42

-. 720

.531

-. 150

,193

-16.1

-18.9

-3.00

-3.5

.930

.640

-2.53

-2.81

2.63

-1.83

-1.84

1.93

-. 360 -. 639

.711

.160

-5S38

-24.7

-20.3

20.4

-3.08

-3.53

3.54

.100[*00 -1.57 .4.3 -. 784

*.6t .9qs

-S.SI

,4:43

4.'?

"TF- TCIS

1.03 .,.IS .- '..041 .73

-2.81

-2.94

2.95

-1.51

-1,61

i,03 1.92

-1.1$

2.17

-1.42

-. 893

1,03

-28.1

-26.8

26.b

-4.S6

-3.74

3077

-2.99

2.14

-2.77

-1.93

1.98

-2.69

-2.04

2.08

-29.8

-28.4

28.4

-7.4?

-5.9S

S.99

IS.3

.161

5.13

-. 430

-4.00

4.32

-22.& -3'.?

17.0

-8.7?

-29.9

"16.9

-29.9

29.&t 29.4

-?0.4

IS.8

40.7

27.7

ZA.T

-2.20

-2.45

2.51

-27.9

-25s:3 *25.*3

2S.3

-1.82

'.97

-34.3

-32.3

32.3

-33.2

-31.?

31.7

1.72 .370

.42.0

,055

-?5. 1 25.'

"L3' - 0553 AP.

23.'

M0L1 - 0003 -.I??

-. 10"

-. 435E-01 -. ]4SL-0! -. 440[-03 .616E-02 .224'-02 -. 679E-42 -. 169E-01 -. P330-01 -. 3o60-0l -.. 9:8-02 -:194f:03 - 4610-02 -. 177c-o2 -. 119E-01 ,A0'0*O! a02 ,*C80*01 8373*002 .f55 .483E-02 .316C0.2 .122E-01
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix C.5

1985-10-22

Case C

C!oD CALCULATWN.OT0*1P0N(N TA UNCEPTAINYT ANALYSIS FOR NRC/ICAAP. ............... *e...........................*........... a...c..~*

FIRST LINE ; DIFFERENCE BETWEEN CALCULAYTO AND IAVERAOED) EXPERIMENTAL OATA AT ENO OF THE INTERVAL

SECONO LIN E E 4 DIFFERENCE OvER T01 INTERVAL

THIR0 LINE I " 4N StOma OVER THE INTERVAL (HOOT MEAN SQUARE OF THE DIFFERENCE)

- CODES - - - - - TIME [NTE*VAL .-..

CALC. FXP. 0.0 * 6.000 - 12.00 - 10.00 - 24.00 - 30.00 - 45.00 - . - 1S.00 ----------------------------------------------------------------------------- :!:! ...------- ------ ------ ------

PIc - k 1 -. 554E-ol .591f-01 .320L-ok .3001-01 -. 260E-01 -. 8741-01 -. 08071-1 -. 327 - .%99F-o .172r-0? .4031-01 *121E-01 -. 142E-02 -. 5361-01 -. 76S1-01 -. 192 .666--l .385E-01 .S51-01 .233C-01 .273E-0I .5S8-01 .77?618 .201

" ?C " 6 4 -. 3?.-el .8941-o- .32VE-01 .S29E-01 -. 960E-02 ".5681-o0 -. 62?7C01 -. 245

-. 1721-01 .461E-01 .729E-01 .340E-01 .762E-02 -. 254E-01 -. 517E0@1 -. 171

.2?71-.1 .594f-02 .819E-01 .3841-01 .210D-02 .2981-01 s2scol .183

P 3C - P 6 -. 666E-01 .5011-01 .111E-01 .541E-01 .280E-02 -. 821E-01 -. 702E-01 -. 266

.235 -. tO&0-01 .414[-01 .327E-01 .754E-02 -. 335E-01 -. 599E.01 -. 184 .706 .390E-01 .485E-01 .431E-01 .279E-01 .391E-01 .61S['01 .194

PD8C - D 4 -?.57 1.37 3.68 -. 644 .972 .250 .469 .220

-2.14 -1.08 2.81 2.36 1.40 .954 .82T .336

%.4e 1.59 3.25 2.80 1.4? 1.05 1.17 .600

PnLC - 0 LP .444 .420 .394 .229 .572 1.43 .215 .173

.405 .421 .453 .368 .377 1.45 .555 .4051-01

.429 .422 .454 .389 .402 1.53 .633 s809E-01

POCC - 0 CO *.0.81 -8.80 .262 5.04 -4.37 -0.56 -2.06 .454

-#.92 -8.99 -4.08 3.62 -. 478 -7.47 -5.04 -. 210

7.94 8.99 5.67 4.17 3.36 7.66 5.29 .913

POuc - 0 UP .. 701 -1.20 -. 590 .112 -. 484 .233 -. 478E01 -.622E-01 -. 793 -. 968 -1.02 -. 374 -. 188 .501 .3761E01 *.457E-01

.985 .983 1.07 .450 .486 .547 .960101 .S04E-01

Po0. - D C.C -. 160 -17.8 -6.03 -2.16 -. 744 6.03 .784 -. 147

-. 161 -S.17 -13.6 -3.51 -. 190 2.50 3.96 -. 127

1.66 7.96 14.5 3.65 1.11 3.54 4.35 .213

PO!C - () 56 -1.60 -1.64 -1.11 -. 3S7 -. 330 -. 459 -. 375 -. 252

-. 233 -1.53 -1.7k -. 700 -. 301 .704E-01 -. 412 -. 467

1.8? 1.54 1.80 .760 .694 .427 .425 .484

-FIC - 1402 -. 723E-01 .8491-01 .198 .28? -. 231 -. 383 -. 604E-01 .464E-01

-. 240 .101c-01 .147 .299 .146 -. 35A -.19? .103E-01

.260 .408C-01 .155 .11 .Z97 .364 .227 .48S[-01

-W?C - 1403 .319c-01 .73S .747 -1.10 -. 207 .452 .669 *S64

-. F64 .223 1.05 -. &6z -.0711.01 .593 .43% .577

.2&4 .306 1.0t .963 1.06 .793 .629 .608

HFIC - A604 -. 201 -. 444E-01 .347 -. 473 .524-01 .100 -. 402 -. 731

-. 201 -. 179 .3b9 -. 316 -. 323[-0] -. 737E-01 -. 419 -. 799

.249 .133 .639 .389 .523 .255 .52 .617

mr!C - 1607 .105E0.0 .739E-01 .352E-01 .2351-01 .795E-02 -. 600[-04 -. 231E-02 -. 268E-01

.934E.01 .7121-01 .5886-01 .3401-01 *11[E-01 .445E-02 -. 46ZE-03 -. 160E-01

.II .716E-01 .602E-01 .342E-01 .133E-01 .681E-02 .283E-02 .183E-01

NF4C - X610 -1.12 -1.13 -. 779E-91 1.16 .171 .983 .801 .742

-. Se5 -1.22 -. 868 .623 .622 .625 .843 .926

.845 1.22 1.00 1.15 .887 .645 .880 .933

rIr - x636 6.3" 2.59 -. 460 -1.20 .244 -. 378 -. 58TE-01 -. 327

-4.73 .962 1.03 -. 630 -. 599 -. 207E-01 .1sl -. 102

6.67 1.48 1.23 1.15 .840 .260 .23S .192

TFlC - T 3 2.45 2.98 4.13 3.00 3.7? -1.23 -4.35 -15.6

1.96 3.21 3.57 4.44 3.52 1.30 -2.45 -9.08

2.01 3.b4 3.b0 4.45 3.53 2.03 2.57 9.65

TFC - T 14 .20z0-01 -. 620 .640 1.78 .5T0 -. 1001-01 -5.59 -16.8

-. 1301-01 .ZaO 1.02 1.29 1.48 1.13 -2.38 -11.3

.775 .572 1.17 1.37 1.84 1.31 3.02 11.8

TF4C - T 15 1.23 2.50 1.25 2.00 1.27 .600 -8.07 -20.3

1.50 1.89 1.55 1.42 1.35 1.12 -3.75 -14.5

1.61 1.95 1.56 1.46 1.39 I.IS 4.54 14.9

TfIC - T 31 7.31 5.60 -. Z90 -1.36 -1.87 -3.03 -2.34 -8.67

2.22 6.33 2.78 -1.36 -1.02 -2.36 -3.09 -6.12 1.3F 6.56 3.48 1.01 1.85 Z.39 3.13 6.32

7rAC - T 34 1.07 2.80 2.37 -. 220 -1.42 -2.45 -3.15 -8.07

.418 1.61 2.53 .862 -1.27 -1.98 -2.66 -S.68

1.09 1.68 2.54 1.12 1.37 Z.02 Z.67 5.90
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix C.6

1985-10-22

- .- nrs - - - TIOE 2INTERVAL - - -

CALC. CAP. 0.0 - 6.000 - 12.00 - 18.00 - 24.00 - 30.00 - 45.00 - 60.00 - 75.00

HTC- TC 1

A.03

*TC - IC 3 ?.58

;-77

NT3C - IC 5 -'.11

14T' - IC 9 -. Q60 -1:43

- 2.'

-2.??

3.20

-. 670

2.048

2.60

-2.00 -3.27

3.2'

-. 670

*.805

.060

2.04 1 .20

2.??

.060

.560

-?0 .5

25.0

-2.92

-2.66

2.70

2.04

2.0v

-2.28

2.30

2-03.02 -1.23

1.134

.230

.658

.514 .705

-25.7

-17.8

127.9

-2.03

-2.59

2.62

1.94

1.71

1.72

-1.46

-1.71

1.73

-. 620 -;870

1.00

.245

.33A

.870

.223

.364

-18.8

-IS,6

IS.S

1.49

1.72

1.73

-1.66

0.67

-. 160

.322

.361

.190

:136

.264

-2.97

-2.30

2.32

.980

1.34

1.36

-2.00

-1.63

1.64

-2.44

-2.6A

2.04

-1.83

.677

.766

"6.50

9,29

•.450 -'2.1

-,900-01 -19.2 .200 25.2

-24.7

-9.S8

11.9

27.9

15.3

17.4

-16.6 -15.7

15.?

-45,*

-'522

42.3

-13.' -18.4

19.0

-35.9

-33.2

33.2

-21.2

-20.5

20.5

HTC- TC12

HT.C - TC15

2.30

1.38

.'67

0.55

-. 2S0

.111

.209

-28.2

-13.1

17.4

.4000-01 -. 320 -31.7

.147 -. 555E-01 -16.0

.358 .202 19.4

PLIC - X661 -28.6

-22.6

23.6

"PIC - Xo8I -. 127 -. l62

.249

-21.9

-20.9

20.9

-22.3

-21.6

21.6

-19.7

-20.7

20.8

-. 43S-01 -. 1450-01 -. 440C-03 .616[-02 .22405-0 -. 679E-02 -. 169E-01

-. 803E-01 -. 366E-01 -. 6980-02 -. 1940-03 .461E-02 -. 7TTE-02 -. 1191-01

.A44f-01 .4080-01 .6550-02 .373E-02 .483E-02 .316E0-2 122-01
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix C.7

1985-10-22

Case D

COnE CALCULAT2ON-TO.EOP[P2NC(iT OATh UNCE8TAIiTT ANALYSIS p0R P4RC/2CAAP.

FIRST LINE I oirDWPrNCE RETwEEM CALCULATED AND (AVERAGEND EAPERINCNTAL DATA AT END Or THE INTERVAL SPCOh.t LINE rmfAN DIFFERENCE ONVER THE IN ,EROA THIRD LINE MEA f S|MMA OVEP TH INTE RVAL kOOT EAdN SQUARE Or THE UIr¥eRFNCE)

- -- - - TIME INTERVAL ----

CALC. tIP. 0.0 - .6000 - 17.00 - 10.00 - 24.00 - 30.00 - 45.0 - 40.60 - T5.04

----------------------------------------------------------------- --------- -----------

P I- - I -. 307-P .IQ3 .lb3 .131 -. ?27E-01 -. 303 -. 42S -.704 -.. oir-.! .9.IE-01 .162 .IS3 .360[-01 -. 168 -.354 -. 556

.593E.o2 .11' .144 .153 .6200-01 .18? .35S .560

P Pý - P *13'E-0I .7?3 .180 .152 -. 6300-02 -.2?? -. 399 -.624 -. 6h30-,: .i3• .214 .173 .566-01 -. 140 -. 32: -,53. .o30r-01 .152 .216 .174 .755E-01 e162 .330 .542

P In - P 4 -. 20S-a1 .lb4 .*bb .1S6 .121E-01 -. 295 -. 404 -. 640 .7E0 -612[-01 .163 .174 .5840-01 -:146 -. 336 -54S .71s .,03 .lb4 .176 .7760-01 .169 .337 .:59

PD --. * 52 1.36 4.10 -.604 .940 .176 .509 .236 -2.07 -1.10 2.95 2.26 1.19 *.96 .790 .43? 4.43 1.00 3.1 2 .68 1.31 1.Os 1.16 .725

POLW - 0 LP .4.? .416 .41Z .387 .536 1.4? .534 ,S41E-01 .*0: *41 .448 .370 .238 1.S3 .a18 .229 .426 .419 .449 .377 .299 1.61 .890 :276

PO•r - D CO -A.?! -4.72 2.74 5.60 -4.42 -0.96 -2.Z9 .351 ".•..9 -l.c0 5.77 -1.21 .7T41 "S.4 .7 318 ?7.5 8.94 5.42 S.97 3.02 7.71 5.70 .961

POUO - 0 UP -. 699 -1.21 -. 631 .611 -. 502 .201 -. 577?E-1 -. 751E-01 .-. 96 -1.07 -. 141 -. 170 .62 .8TI6-12 -. 5760-01 .9'. q66 -1.11 .4*5 4.9. .31 .79%E-ol .61S(-01

POný- 0 PC -.PaI.v1 -17.8 -7.74 0*.30 -1.13 5.71 .66% .140

-.13* -5s04 -14.4 -S.97 -2.78 1.44 3.89 -. 300'-01 I .4' 7.40 15.3 6.02 3*34 3.03 '.28

Po0D - P S6 -. 3 -1. -1.16 .2r0 -. 142 -. 471 -. 63? -. 343 -.71P -2.56 -1.b3 -.5z1 -,24' .8610-02 -. 696 -503 2.P4 1.•' 1.67 .656 .360 .436 .S07 .50a

MV 2 - 602 -. 7022-01 .868E-01 ,.22 .282 -. 210 -.4?s -. 621E[02 .403E-01 -.23? .119E-01 .154 .276 .929E-02 -.3:0 -.201 .740f-0Z ?177 .,130-01 .166 .263 .188 I3s6 3237 .483E-01

Nrf - RA03 .. €7r2 .70T .053 O.qh -. 615 -. 242 .838 .434 -.271 .707 ."99 -. 2P -. 2S5 .5S2 .s5 .611 .46' .791 2.01 1.04 1.25 .729 .67.. .680

Wr -. -. 204 -. 7VTE01 -. 195 -.132 .600 .253 -.366 -.634 -. 114 -. 138 .102 -. 36b .164 .126 -. 367 -. 760 .254 .140 .420 .407 .283 .300 .51? .?80

- A;0 0607 .70SE-02 .7390-01 .590E-01 .394E-01 .0686-0Z -. 343(-02 -.536C-01 -. 8510-01

.9340-02 .7120-01 .79SE-0l .5670-01 .2060-01 -. 1310-01 -.43%E-01 -. 7070-01 .101 .7160-02 .b9CC-9 0 .570I-01 .234'E01 .194E-01 .4330-I1 .7S1-01

F.Fr - 1621 -1.11 -1.12 -. 420 .990 .845 1.09 1.05 .550 -.567 -2.23 -.PNO .908 .668 .,03 .63z .604 .831 1.23 .553 1.36 .532 .630 .876 .640

-t - x63b .- 9q? 2.57 -. 753 -1.21 .290 -. 390 .560o°02 -. 261

.7? .967 .847 -. 791 -. 568 -. 117E-01 .214; -. 676E-01 6.04 1.48 1.13 1.17 .636 .264 .232 .162

TFln - T 3 3.5f 3.26 '.?6 S.34 3.77 -4.6S -11.1 -25.9 7.01 3.4? 3.90 4.61 4.32 -. 400 -7.44 -17.7 7.06 3.64 3.93 4.62 6.37 2.66 7.63 18.2

Trp - T 14 .370 .730 2.2o 2.9 .620 -3.46 -12.3 -27.1

.'3'r.ol .920 ?.47 2.67 2.12 -. 580 -7.3@ -19.9 .729 1.11 2.53 2.91 2.43 1.63 7.87 20.4

Tr.- - T 11 1.63 3.75 ?.e5 3.24 1.33 -3.03 -14.8 -3006

2.o0 ?.?s 3.00 3.02 2.00 -. 59S -8.75 -23.1 2.01 7.62 3.01 3.03 Z.09 1.39 9.'1 23.S

Trip - T 31 7.09 6.25 1.33 -. 130 -1.63 -6.43 -9.14 -19.0 1.:? 8.35 •.6 .273 -1.15 -4.05 -8-147 :,QT .. 9.30 .461 1.32 4.27 6.15 1.9

TFc- . T 34 1.75 4.8S 4.03 .920 -1.28 -5.83 -9.77 -18.3

.193 2.62 5.14 2.53 -. 669 -3.63 -7.S9 -14.2 1.64 2.9S 5.15 2.71 1.01 3.57 7.65 24.4
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix C.8

1985-10-22

CALC. (EP.

- - - - TIME INTERVAL .......

1,. - 6.000 * 1?-00 = 38.00 - 24.00 - 30.00 - 45.00 - .60,0 * 75.00 -- --- -- -- ------ -- - --------- --- -------- - ------ - - ------ - -------- -- ------ --- ------ -------

HTP71 - TC 3

MTn- TC S -14

.4.3S

1T474 - TCa -. 6140

- TCI? 1.6p

41'.D - ICts 1~

1 .'01

P130 X6161 ?8

- XAC 80 -. 12T

Ok I1

- 311%

3.98 3.16

3. 3

-1.09

-2*66 2.63

.430

-. 9310-01

.515

2.13 1.9?

1.9'

I .95

1.64

1.65

-22.0

-2S 1 25.2

-. 435*-0

-. 8o30-01 .9440-01

-1.63

-3.36

3.29

3.37

3.39

-. boo

-. 944 ,993

-. 180

.3,2

:bib

1.65

1.77

3.81

1,9'

1.86

1.90

-16.7

-18,2

18.3

-.314E-03

-. 3860-01

,,08(*01

-. 700

-1,31

3.29

3.21

-. 100

,302

.720

.609

.?65

1.701

1.69

1.70

2.15

1.74

1.76

-17.1

17.1

-. 440E-03

-. 490E:02

,65S0-02

-2.05

-1.43

1 .54

1.69

2.57

-1.24

-,855

.7000-01

.689

.650

*.00

.938

1.0'3 .290

1.03

-Z3.9

-22.a

22.9

.616E-02

-. 19 4-03

.3?30E 2

-4.16

-3.72

3.94

-2.27

-*153

O ?I

-S.26

-3.13

3.33

-3.67

1.91

-3.66

-1.36

1.77

-3.68

1|.47

1.87

-24.1

-23.3

23.3

.2241-02

:461[-02 .463E-02

-A.79

-7.36

7.39

-. 940 -3.80

3.90

-13.5

-9.52

-37*9

-21,6

26.1

-23.7 -15*?

18.6

:33:4

22..

-21.6

-22.7

22.7

-. 679E-92

177[08?

.316C 2

-3.03

-6.53

8.92

27.6

15.4 17.1

-15.6

:36.6

35:0

-43,7

-39.9

40.0

-13.2

"16.0

36.6

-36.9

-35.0 35.0

-22.5

-22.1

22.1

0.169E-01

*.119E001

,122E-01
STUDSVIK ENERGITEKNIK AB STUDSVIK/NR-85/99 Appendix C.9

1985-10-22

P JA PRESSURE LUWER PLENUM (P 3101) CASE A

P 2A PRESSURE* UPPER PLENUM IP 5201). CASE A P 3A PRESSURE. bREAK INLET (P 96011 CASE A PO0A DIFF PRESSURE, COAE INLET RESTRICTION (P 3301 - P 401) CAS POCA 01FF PRESSURE* CORE (FROM P 401 - P 51011 CASE A PODA OIFF PRESSURE, O0.NCOMER (FROM 0 7103 - P 72011 CASE A POLA DIFF PRESSURE. LOWER PLENUM (FROM P 3101 - P 3301) CASE A PDUA DIFF PRESSURE, UPPER PLENUM (FROM P 5101 - P 5201) CASE A POSA 01FF PRESSURE, STEAM SEPARATOR ORIFICE (P S201 - P 5?021 C

TSUA SUBCOOLINO, BREAK INLET (TEMPG 9101 - TEMPF 91011 CASE A mPIA CORE HEATING PowER (CMTALVAR 571 CASE A

HLIA MEAT LOSS FROM PASSIVES (CNTRLVAR 53) CASE A mFIA MASS FLOW RATE, BYPASS (MFLOWJ 117) CASE A MF2A MASS FLUW RATE, I.L. PUMP (MFLOwJ 20102) CASE A

MF3A MASS FLOW kATE, B.L. PUMP (MFLOWJ 20202) CASE A

,F0A MASS FLOW kATE, H.L. VESSEL INLET (MFLOWJ 9702) CASE A

WFSA MASS FLOW RATE, STEAM RELIEF (NFLOWJ 404) CASE A MFGA MASS FLOW RATE, BREAK (MFLOWJ 152) CASE A RHIA FLUID DENSITY, CORE POTTOM (RHO 04011 CASE A

RH2A FLUID DENSITY, VESSEL BOTTOM (RHO 3101) CASE A RM3A FLUID DENSITY, RREAK (RHO 9601) CASE A ,TIA MEAN CLAD TCMPERATujE, LEVEl. I (HTTEMP 401000105) CASE A t4T2A MEAN CLAD TEMPERATURE, LEVEL 3 (HTTEmP 403000105) CASE A mT3A MEAN CLAD TEMPERATURE, LEVEL S (MTTEMP 404000105) CASE A mT4A MEAN CLAD TEMPERATURE, LEVEL 9 (HTTEMP 406000105) CASE A HTSA MEAN CLAD TEMPERATURE, LEVEL 12 (MTTEMP 60T000105) CASE A HT6A MEAN CLAD TEMPERATURE, LEVEL 15 (MTTEMP 410000105) CASE A TFIA FLUID TEMPERATURE, CORE INLET (TEMPF 3301) CASE A TFA FLUID TEMPERATURE, CORE OUTLET (TEMPF 5101) CASE A TF3A FLUID TEMPERATURE, DOWNCOMER BOTTOM (TEMPF TI70) CASE A TF4A FLUID TEMPERTURE, UPPER PLENUM (TEMPF 5201) CASE A TFSA FLUID TEMPERTURE, BREAK INLET (TEMPF 9601) CASE A

CPUA CPUTIME CASE A

MATA TOTAL MASS, IN SYSTEM CASE A

MAEA MASS ERROR CASE A

mLIA BREAK TOTAL MASS LOSS (ChTRLVAR 55) CASE A

P 3 PRESSURE, LOWER PLENUM (PI 3) - EAPERIMENT P 4 PRESSURE, UPPEF PLENUM jPT 4) - EXPERIMENT P 6 PRESSURE, BREAK INLET (PT 6) - EXPERIMENT

O 4 01FF, PRESSURE, LJRE INLET RESTRICTION (OPT 4) - EXPERIMENT

O 56 DIFF. PRESSURE, STEAM SEPARATOR ORIFICE (nPT 56) - EXPERIME

O LP DIFF. PRESSURE, LOWER PLENUM (OPT 2 * DPT 3 -DPT I) - EXPE

D CO DIFF. PRESSURE, CURE (OPT 5 o OPT 6 . .. ,. . OPT 12) - EXPE

0 UP 0IFF. PRESSURE, UPPER PLENUM (OPT 13 * OPT 16) " EXPERIMENT

O DC DIFF. PRESSURE, OOwNCOMER (OPT ?I o .... . OPT 30) - FXPERI XbO? MASS FLOW RATE, BYPASS (CALCULATED) - EXPERIMENT X603 MASS FLOW RATE, I.L. PUMP (CALCULATED) - ExPERIMENT

X604 MASS FLOW PATE, H.L. PUMP (CALCULATED) - EXPERIMENT

160? MASS FLOW RATE, STEAM RELIEF (CALCULATED) - EXPERIMENT

X610 MASS FLOW RATE, WL. VESSEL INLET (SPOOL PIECE I10) - EXPEN

X636 MASS FLOW RATE, BREAK FROM T2 INVENTORY (CALCULATED) - EXPE

X661 MASS LOSS, BREAK FLOW kECIEVER (CALCULATED) - EXPERIMENT

Xb01 ELECTRIC POWER, CORE (CALCULATED) - EXPERIMENT

T 3 FLUID TEMPERATURE, CORE INLET (TE 3) - EXPERIMENT T ]A FLUID TEMPERATURE, CORE OUTLET (TE 14) - EXPERImENT

T 15 FLUID TEMPERATURE, UPPER PLENUM (TE 15) - EXPERIMENT T 31 FLUID TEMPERATURE, DOWN COMER BOTTOM (TE 31) - EXPEkIMENT

T 34 FLUID TEMPERATURE, BREAK INLET (TE 341 - EXPERIMENT TC I MEAN CLAD TEMP., LEVEL I (TI91 T206 T211 T246) - EXPERIMENT

TC 3 MEAN CLAD TEMP*, LEVEL 3 (TICS T183 T243 T249) - EXPERIMENT TC S MEAN CLAD TEMP., LEVEL 5 (T202 T227 T232 T23T T252) - EXPER TC 9 MEAN CLAD IEMP,. LEVEL 9 (T102 T13T T16e TIT2 TIET T197 T27 TC12 MEAN CLAD TEMP.. LEVEL 12 (TiIS T123 T128 T168 T223) - EXPE TCIS MEAN CLAD TEMP., LEVEL 15 (T175 T190 T275) - EXPERIMENT

NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER (Assignedby TIDC, add Vol No,, ifsAny (2.84)

NRCM 1102. NUEG/IA-O005

3201,. 3202 BIBSLIOGTRAPHIC DATA SHEET S-SVf/NR-85/99

SEE INSTRUCTIONS ON THE REVERSE,

2. TITLE AND SUBTITLE 3 LEAVE BLANK

Assessment of RELAP/MOD2, Cycle 36, Against FIX-II

Split Break Experiment No. 3027 4. DATE REPORT COMPLETED

MONTH YEAR

5. AUTHOR(S)

6. DATE REPORT ISSUED

MONTH YEAR

John Eriksson September 1986

7. PERFORMING ORGANIZATION NAME AND MAILING ADDRESS (McludeZlo Code) S. PROJECTITASKIWORK UNIT NUMBER

Swedish Nuclear Power Inspectorate 9. FIN OR GRANT NUMBER

P. 0. Box 27106

S102 #52 Stockholm, Sweden

10. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (IncludeZip Code) Ila. TYPE OF REPORT

Office of Nuclear Regulatory Research Technical

U.S. Nuclear Regulatory Conmission b. PERIOD COVERED O.,,clus.. dares)

Washington, DC 20555

12. SUPPLEMENTARY NOTES

13. ABSTRACT (200 words orless)

The FIX-II split break experiment No. 3027 has

been analyzed using the RELAP5/Mod2 code. The code

version used, Cycle 36, is a frozen version of the

code.

Four different prediction calculations were

carried out to study the sensitivity on various

parameters to changes of break discharge, initial

coolant mass, and passive heat structures. The

differences between the calculations and the

experiment have been quantified over intervals

in real time for a number of variables available

from the measurements during the experiment.

The core inventory expressed by the differential

pressure over the core was generally underpredicted.

Dryout times were generally overpredicted, probably

due to differences in the used dryout correlation.

14. DOCUMENT ANALYSIS - a, KEYWORDSIDESCRIPTORS 15 AVAILABILITY

RELAP5/MOD2 STATEMENT

FIX-II

ICAP Code Assessment Unimifted

16. SECURITY CLASSIFICATION

ITha page)

b. IDENTIFIERS/OPEN-ENDED TERMS Unclassified

ITh,s repO,)

Unclassified

17. NUMBER OF PAGES

18 PRICE


UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

SPECIAL FOURTH-CLASS RATE

POSTAGE & FEES PAID

USNRC I WASH. D.C

PERMIT No. G-67

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