NUREG/IA-0016

Intemational

Agreement Report

Assessment of RELAP5/MOD2,

Cycle 36.04 Against FIX-Il

Guillotine Break Experiment

No. 5061

Prepared by

J. Eriksson

Swedish Nuclear Power Inspectorate

S-102 52 Stockholm, Sweden

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

July 1989

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

agreement for the exchange of technical information.° Neither

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-0016

• Agreement, InternatlionalReport

Assessment of RELAP5/MOD2,

Cycle 36.04 Against FIX-Il

Guillotine Break Experiment

No. 5061

Prepared by

J. Erlksson

Swedish Nuclear Power Inspectorate

S-102 52 Stockholm, Sweden

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

July 1989

Prepared as part of

The Agreement on Research Particlallon and TechnIcal Exchange

under the Internatonal Thermal-Hydraulc Code Assessment

and Apglcatlon 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/NP-86/109

STUDS'.'IX ENERGI"T.EYNIK AB 1986-10-28

SKI Project 85026, 13.3-917/84

John Eriksson Swedish Nuclear Power Inspectorate

ICAP

Assessment of RELAP5/MOD2, Cycle 36.04 Against

FIX-II Guillotine Break Experiment No 5061

ABSTRACT

The FIX-I1 guillotine break experiment No. 5061 has

been analyzed using the RELAP5/Mod2 code. The code

version used, Cycle 36.04, is a frozen version

of the code.

Four different calculations were carried out

to study the sensitivity of initial coolant

mass, junction options and break discharge

line .nodalization. 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 break mass flows were generally underpredicted at the same time as the depressurization rate

was overpredicted.

Appreb 7

STUDSVIX ENERGITEXNIK AB STUDSVIK/NP-86/109

1986-10-28

LIST OF CONTENTS

Paae

1. INTRODUCTION 3

2. FACILITY AND TEST DESCRIPTION 5

2.1 Test facility 5

2.2 The experiment 7

2.3 Measurement uncertainty 9

3. CODE AND MODEL DESCRIPTION 10

3.1 The code features 10

3.2 The Input Model 11

4. THE BASE CASE CALCULATION 14

5. SENSITIVITY RESULTS AND DISCUSSION 18

5.1 Case B 18

5.2 Case C 20

5.3 Case D 21

5.4 Discussions 21

6. RUN STATISTICS 23

7. CONCLUSIONS 24

REFERENCES 26

FIGURES 28

TABLES 35

APPENDICES

A. Input listings

B. Data comparison plots

C. Calculation of data uncertainties

D. Description of the accompanying data package
i
STUDSVIK ENERGITEKNIX AB STUDSVIK/NP-86/109 3

1986-10-28

1. INTRODUCTION

An International Thermal-Hydraulic Code Assessment and Applications Program (ICAP) is during

the present years being conducted by several

countries under the coordination of the USNRC

(1). The goal of the program is to make quantitive statements regarding the prediction capabilities of current best-estimate thermalhydraulic computer codes. Such codes have been

used for many years as state-of-the-art instruments to study and verify numerical and

correlative computation models against results

obtained in experiment. Some of those codes

have reached a high degree of sofistication and do comprise models for mainly all

processes which are essential to thermalhydraulic scenarios in nuclear reactor application. So far, however, those codes did not

achieve the status as reactor licensing tools,

such as fulfilling the Appendix K rules (2),

although they are often applied for other calculations. The present ICAP aims to quantify

uncertainties of the codes to allow their use

for licensing purposes.

Sweden's countributions to ICAP encompass assessment calculations using the two thermal-hydraulic

codes TRAC-PWR (3) and RELAP5/MOD2 (4). The assessment calculations are conducted by Studsvik Energiteknik AB sponsored by the Swedish Nuclear Power

Inspectorate.

The calculation presented in this report concerns a FIX-II experiment for a 200 % doubleended guillotine break. This experiment,

Test No. 5061, was conducted during the

second experimental period. Table 1 gives a

short information about experiments done during

that period.
i

STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 4

1986-10-28

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 included in

Appendix B. Results of the statistical

analyses of differences between experiment and

predictions for discrete time intervals are

included in Appendix C. Finally, Appendix D

describes the data package on magnetic tape prepared for use on the ICAP evaluation work.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 5

1986-10-28

2. FACILITY AND TEST DESCRIPTION

The FIX-I integral test facility was completed

at the end of 1981. It has been run by Studsvik

Energiteknik AB under contract to the Swedish

Nuclear Power Inspectorate. The experimental

program comprises investigations of the fuel-tocoolant heat transfer. Various blowdown and pump

trip situations conceivable in Swedish BIWR's are

simulated.

2.1 Test facility

The test facility itself 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-Il test facility may be obtained

from Ref (5), which also provides additional refer

ences where various problems pertaining to the

construction period are discussed. Therefore, on)y

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.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 6

1986-10-28

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 is diverted

through a control 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 space 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/NP-86/109 7

1986-10-28

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 flows (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 blowdown. 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
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STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 8

1986-10-28

to 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 guillontine break test

No. 5061, the transient ends 27.3 s after opening

of the break.

In the present FIX-I experiment, the speed of

the pump in 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

explicitly controlled.

The break flow escaping through the fast opening

break valves, Figure 1, are discharged into the

receiving tanks, T2 and T3. Initially, the tanks

are partly filled with cold water for efficient

pool condensation of the break flows.

The guillotine break assembly consists of one

connection to the line from pump P2 and one

connection to the lower plenum. Break flow

limiting orifices, downstream of the break

isolation valves, consist of an exchangeable

conical inlet part followed by a restriction

pipe. In experiment No. 5061, each restriction

pipe and flange diameter were 21.6 mnm corresponding to a 100 % area of one recirculation

line. The total break area for both connections

is thus 200%.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 9 1986-10-28

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.

The main measured parameters for the steady state

before break are reproduced from Ref (6) 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 7 s

due to uncertainties in 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.

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, mostly mass flows, are given in Table 2b.

The pump speeds are measured using a tachometer

of a 1 r/s accuracy. The pump characteristics

were verified against the manufacturer's data

for cold water single phase operation.
STUDSVIK ENERGITEKNIX AB STUDSVIK/NP-86/109 10

1986-10-28

3. CODE AND MODEL DESCRIPTIONS

The assessment calculation for the FIX-Il

experiment No. 5061 was done using the

RELAPS/Mod2, Cycle 36.04 code received at the

beginning of February 1985. The code was implemented in June 1986 on a CDC 170-810 computer.

The descriptive document available for this code

at the time of preparing the calculation input

was the rather detailed code manual (4) also

explicitly containing an input data requirements

manual. The code features are discussed in

Chapter 3.1.

The calculation model is closely related to the

two previous ICAP calculations for the FIX-I!

experiments No. 3027 Ref (7) and No. 3051

Ref (8). The main differences in the input

concern the double-ended break geometry. Details

of the input are discussed in Chapter 3.2.

3.1 The Code Features

An extensive code description for the RELAP5/Mod2

is given in the Ref 4. The main characteristics

of the code are summarized in Table 3.

Since the RELAP5/Mod2 code is primarily developed

for PWR application, the question arises whether

some important features are missing in the code

for a BWR-type application like the present

FIX-II experiment. One such feature could be

deficient modeling of droplet flow in RELAP5/MOD2

for reflood and core top spray. The FIX-Il

facility does not have a core top spray cooling

as the facility is designed for experiments until

end of blowdown only. The steady state cooling,

however, is accomplished by a cold water injection
STUDSVIK ENERGITEKNIK AE STUDSVIK/NP-86/109 11

1986-10-28

at the top of an internal condenser space above

the core and the steam separator. The condenser

space is voluminous; and it is assumed that the

condenser spray partly vaporizes while the rest,

reaching saturation, has no impact on the core

behaviour. Modelling of droplet flows is therefore

in actuality not addressed in this study.

3.2 The Input Model

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

several previous calculations for FIX-I1 experiments using previous RELAP5/Modl code versions

(7 and 8). The nodalization diagram for the

geometric modelling used is shown in Figure 5.

Figures 6 and 7 depict the modelling of the

geometry of the test facility.

To reproduce fundamental measured steady state

quantities, see Table 4, the input for the steady

state runs was modified by some additional

components and control systems:

I To obtain the steady state dome pressure,

a time dependent volume outside the opened

steam relief valve was added. This volume

had the experimentally measured dome

pressure.

II The speed of the pumps P1 and P2 were

controlled using the RELAP5 control

system to reproduce the measured mass

flows.

III To divert 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

controlled to give the experimental bypass

mass flow. When entering into the

transient calculation, the valve setting

was fixed.
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STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 12

1986-10-28

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 adjust

the collapsed level by water addition

depending on the level offset.

V To eliminate the mass flow of the

pressurizer discussed under item I the

common temperature of the condenser spray

water and the feedwater was adjusted within a span of 2K from the measured

temperature. The level control flow, item

IV, then also became negligible.

For the condenser spray water and the feedwater

temperature control (item V) had not been

applied for any previous FIX-I1 calculation. For

the present experiment this was necessary

because of an inconsistency in the heat balance

in the measured initial conditions, Table 4. The

temperature of the coolants, had to be increased

by 1.8 K to match the heat balance. This is,

within the measurement error limits for fluid

temperatures, Table 2a.

Another difference from the previous FIX-II

calculations is the lower fluid temperature in

the two break flow lines Plot B.34. The experimental temperature on the plot obtained at the

T-piece measures the recirculated water temperature under steady state. The first calculations

indicated too low break flows during the first

one or two seconds. By the lower fluid temperature in the discharge lines, the initial break

discharge was better predicted. For temperature

stability in the initial steady state the

boundary heat structures of the discharge pipes

were assumed to have insulated outer boundary

conditions.
STUDSVIK ENERGITEMNIK AB STUDSVIK/NP-86/109 12

1986-10-28

The input of the steady state was in the present

calculation made as complete as possible to also

cover the transient actions. The steady state

controls were disconnected by a first trip and

the remaining trips followed to simulate the

system actions. In the transient restart the

first trip is set at zero time with a new

initiation of the time scale. Until the second

trip, which is the one initiating the physical

transient, the transient calculation is run at

the initial state as test for stability. The

sensitivity calculations also start with steady

state calculations from inputs having complete

sensitivity updates.

The discharge flow from the downcomer side break

did in the first test calculations give rise to

some doubt about the pump P2 head curve dependence

of the volume flow (9). From the initial singlephase discharge flows of some split break FIX-I1

experiments (Nos 3025, 3027, 3031, 3051 and 3061

at lower flow rates) the accuracy of the most

important parts of the single-phase head curves

were confirmed.
STUDSVIK ENERGITEKIIIK AB STUDSVIK/NP-86/109 14

1986-10-28

4. THE BASE CASE CALCULATION

The transient calculation of the base case

(called Case A) was based on the restart file

obtained from the steady state calculation. To

verify the quality of the steady state, the

opening of the break was delayed by 5 s.

The calculation of the transient was carried out

without any particular problems. The smooth lapse

of the CPU-time, Plot B.37 and of the computation

mass error, Plot B.39, indicate that.

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 1. Those parameters

are listed in Table 8 and the comparison plots are

reproduced in Appendix B. Since some of the

parameters are not available from the experimental

data, only comparisons between different

calculations are shown in some of the plots. For

the internal mass flow comparisons, it should be

emphasized that the experimental data are not

reliable after voiding has begun which for most

measurements occurs about 7 s after the break

opening.

The spray flow and the feedwater valves, were

closed immediately after the break, see Table 5.

The break signal also initiates closure of the

valve in the broken recirculation line (V103).

There is a good agreement between calculation and

experiment of the mass flow rate through the

steam relief valve, plot B.28. However, the break

mass flows which in the experiment are measured

by the increasing content of flow receiving

tanks, plots B.32 and B.33, have obviously been

underestimated in the base case calculation.
STUDSVIK ENNERGITEKNIK AB STUDSVIK/NP-86/109 15

1986-10-28

A problem with the determination of break flow

should be noted. The discharge flows enter two

collection tanks filled with a large amount of

cold water. The discharged mass is evaluated

using the pressure difference from the bottom to

the water level in the tanks. The discharge

pipes also include perforated tubes inside the

collecting tanks. The volumes of these pipes

amount about .037 m3 for the downcomer side and

about .042 m3 for the vessel side tubes. These

volumes are probably steam-filled and small steam

jets may even occur outside of the perforated

parts during the blowdown. The actual level fall

back at end of the transient when the break

valves close, is less than the volumes of the

perforated tubes. Consequently, at the end of

the transient same water was present in each of

the discharge pipes.

It can be concluded that the bias in the break

mass loss must have varied during the transient.

However, the initial bias, was apparently nearly

the same as the bias near the end of the test.

The mass flow rates which are obtained from the

differentiated mass inventory history may contain

large errors in instantaneous values.

The calculated system pressure, Plots B.21, B.22

and B.36, is in the base case decreasing too

rapidly. The depressurization rate responds on the

break mass flow and quality, on the continued

system heating and on the initial fluid mass as

the main quantities. The entalpy increase comes

partly from the core and partly from the by-pass

heating. The filler body space cooling is also

rather well defind during the transient becuase

of the know intitial cooling capability. Least
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 16

1986-10-28

well known is the heat from passive structures.

Plot B.3 shows that this heating is considerable

and is even larger than the decay heat after

13 s. The heat structure modelling has been

developed based on previous FIX-I1 calculations

for smaller break areas. From the results of

these calculations the heat structure modelling

can be assumed to be adequate. Therefore, errors

in the initial system mass content is suspected

to be responsible for the underpredicted system

pressure. The first sensitivity calculation is

devoted to this question.

The predicted core inlet temperature, Plot B.11,

and the core outlet temperature are close to

saturation temperatures. The same applies for

other system fluid temperatures, Plots B.19,

B.20 and B.34. The core inlet temperatures show,

Plot B.11, larger initial subcooling in the

experiment than is predicted. A minor part of

the discrepancy is a consequence of the slight

overtemperature of the feedwater necessary to

maintain the initial heat balance, see Chapter 3.2.

As the core inlet mass flow reverses immediately

after break, Plot B.2, a faster core inlet

temperature rise in the experiment had been

expected than Plot B.11 shows.

Plots B.1, B.14 and B.29 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.

The fluid inventories of the core, Plot B.13,

the upper plenum, Plot B.17, the downcomer,

Plot B.15, and of the lower plenum, Plot B.16,

are compared as differential pressures which are

directly measured in the experiment.
STUDSVIK ENERGITSKNIK AB STUDSVIK/NP-86/109 17

1986-10-28

Notable is the discrepancy in the lower plenum

pressure difference in the time interval up to

5 s, Plot B.16. This, together with the discrepancy in the differential pressure over the core

inlet restriction, Plot B.2, verifies that the

vessel inlet mass flow, Plot B.26, is larger

than predicted for this time interval. The mass

flow escaping from the lower plenum towards the

break appears in the experiment not to be

completely consistent with the break flow

(compare with Plot B.33).

The comparisons of the rod clad temperatures are

done at the clad inner surface which is closest

to the thermocouple positions of the electrically

heated rods in the experiment. Above the core

midplane, levels 7, 9, 12 and 15, the dryouts

are predicted to occur 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 correlation using 1-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. The latter gave

better agreement with FIX-data. The delay in the

calculated dryouts is probably a result of the

critical heat flux correlation rather than of

core voids.
I

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STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 18

1986-10-28

5 SENSITIVITY RESULTS AND DISCUSSIONS

By variation of the calculation model from the

base case, Case A, three additional calculations

were carried out. These sensitivity calculations

are characterized by the following changes:

Case B Increased initial liquid mass

Case C As Case B and changes in the pumps outlet restriction modelling

Case D As Case B and a denser nodalization on

the downcomer side main break flow path

5.1 Case B

The base case calculation failed to predict

several parameters reasonably well. The

depressurization did proceed too fast while the

fluid mass discharged through the breaks was

underpredicted. The reason could be an underestimate of the initial fluid mass which corresponded to the measured downcomer collapsed

liquid level. The same problem had previously

been recognized for the FIX-II split break

No. 3027, Ref (7).

The underestimate of the initial mass is mainly

a consequence of the calculated droplet content

in the spray condenser. The condenser constitutes

about three quarters of the total system volume.

The water droplets entering the condenser before

experiment are formed by injection nozzles

giving droplet diameters smaller than assumed by

the code which uses a fixed Weber-number for the

annular mist flow regime. For the FIX-I experiment No. 3027 an underestimate of the condenser

water mass by 26 kg had followed from an estimated

difference in the droplet falling velocity

Ref (7).
STUDSVIK ENERGITEKNIK AB STUDSVIX/NP-86/109 19

1986-10-28

The total loss of mass through the two guillotine

breaks and the steam relief valve was estimated

to have been 298 kg in the experiment Ref (6).

The remaining mass in the system after test end

is not accurately known. The lower plenum

volume, however, contains no water after test

termination. No water could be identified

elsewhere in the system. Thus, assunting saturated

steam in the system implies additionally 12.5 kg

which added to the total transient mass discharge

gives an initial system mass of 310 kg.

In the split break calculation for the FIX-II

experiment No. 3027 water had been added by

assuming a higher initial water level in the

downcomer than measured in the experiment. For

the present calculation it was assumed that the

higher water content in the condenser was a

consequence of a lower droplet velocity in the

experiment as compared to the water velocity

predicted by the code. This means that the water

transit time through the condenser volumes

should be extended. Therefore the lengths of the

condenser volumes 11 and 12, see Figure 5, were

increased by a common factor while retaining

their volumes. A length factor of 4.8 gave an

initial mass of about 314 kg. The factor 4.8 was

just a little less than that factor by which the

code would start water accumulation in the

condenser.

The results from the Case B calculation did

generally compare better with the experiment

than the base case results. The depressurization,

Plot B.22, was fairly well predicted. The vessel

side break flow, Plot B.33, turned out quite

well while the downcomer side break flow, Plot

B.32, still was underestimated.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 20

1986-10-28

5.2 Case C

The break discharge from the vessel side compared

well in the Case B with the experiment, Plot

B.33, while that from the downcomer side, Plot

B.32, still was underestimated. There were no

obvious reasons to introduce additional discharge

coefficients since piping geometries close to the

two break regions were very similar.

From the downcomer to the break the fluid passes

the pump P2 outlet restriction. A pressure loss

of more than .5 MPa is caused by the restrictions

during the transient. An increased flashing in

the pipes downstream of the restriction could

produce different discharge conditions compared

to the vessel side break opening.

The outlet restriction at the pump P2 has a diameter of 22 mm which is nearly the same as the

diameter of the break opening. The junction

options used at the previous two calculations

had been choked flow, smooth area change and

unequal phase velocities. In addition a flow

loss coefficient also used in some previous

applications had been utilized. With this

modelling of the flow restriction the pressure

drop had been slightly overpredicted during the

first part of the transient in previous calculations.

The pressure loss of the pump P2 outlet restrictions had been measured at various flow conditions

during the running-in experiment Ref (9). A best

fit loss coefficient was determined as:

= 347 x Re 0 5 6
STUDSVIK ENERGITEKNIK AB STUDSVIX/NP-86/109 21

1986-10-28

Assuming a water flow of 12 kg/s to be representative for the first part of the transient a

loss coefficient of 165 was calculated. A test

calculation showed that assuming abrupt area

change with choked flow, and no explicit extra

loss coefficient, gave just that loss coefficient.

For the Case C calculations these junction

options, also assuming homogeneous .two phase

flow and the restriction areas as in the experiment, were used at the outlet restrictious of

both recirculation pumps.

5.3 Case D

The Case D sensitivity calculation addresses the

nodalization density. The steam separator

(vol 21), the downcomer (vol 71), and broken

line (vols 95 and 96) volumes were on the

downcomer side further divided to give about the

double amount of nodes. These model changes were

done to the Case B input data deck.

5.4 Discussion

The experimental rod temperatures in the plots

B.4 through B.10 are mean values of all available

temperature measurements at the individual core

levels. The absolute maxima of the rod temperatures measured at each level are indiciated on

the plots. The individual temperature maxima at

a level do distribute over ranges of even more

than 100 K. Plots of the individual rod temperature measured in the experiment are found in Ref

(6).
STUDSVIR ENERGITEKNIK AB STUDSVIK,'NP-86/109 22

1986-10-28

In view of the temperature distribution in the

experiment the predicitions obtained from the

calculations Cases A, B and C are acceptable at

the high peak temperature levels. At the lowest

core level, Plot'B.4, all the predictions failed

with the exception of the very early temperature

rise. Actually, one rod close to the box shows a

similar level 1 temperature behaviour as the

predictions. The reason for the disagreement to

the other rod temperatures at the lowest core

level may be due to three-dimensional flow

effects or to the erronesously early core inlet

flow reversal.

The quite different core temperature predictions

in the Case D calculation, using a denser

nodalization in the downcomer side discharge

path, is remarkable. The depressurization rate

of that calculation was most badly predicted

during the later half of the transient but

rather good during the times of high clad

temperatures. No core data like the fluid

density at the bottom, Plot B.1, the boundary

fluid temperatures, Plots B.11 and B.12, or the

core pressure difference, Plot B.13, are in the

Case D results significantly different from the

previous calculation cases. Typical of the

Case D calculations are lower break flow fluid

densities, compare Plots B.14 and B.29, causing

a larger amount of remaining water in the core

although the break flow was similar to that of

the previous calculations.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 23

1986-10-28

6. RUN STATISTICS

The transient calculation model used with the

base case RELAP5/Mod2 prediction for the FIX-II

test No. 5061 was modelled by:

60 volumes

62 junctions

70 heat structures

The volumes number includes two pump components

and six time dependent volumes and among the

junctions there are three valve components and

four time dependent junctions.

The computer efficiency is summarized in Table 7

from the Major Edit printouts, see also Plot

B.37. The table also gives the number of time

step reductions from requested time steps forced

by the code internal stability control.

The transient calculation needs were:

computer time CPU = 1 289 s

number of time steps DT = 726

number of volumes C = 60

transient real time RT = 28 s

from which also a code efficiency factor (3) of

CPU x 103 = 29.6 C x DT

is obtained. The computer used was a Cyber

170-810.
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 24

1986-10-28

7 CONCLUSIONS

A double ended quillotine break in the FIX-I1

facility was assessed in the present calculations using the RELAP5/Mod2 code. Four calculations were carried out; one base case and three

sensitivity calculations with variations in

initial mass content and nodalization.

In the steady state a small inconsistency with

the heat balance appeared using the initial

conditions from the experiment. Using previosly

evaluated data for the heat losses, a 1.8 K

hotter feedwater temperature had to be assumed.

This is within the experimental uncertainty.

Concerns about the system total mass and pressure

behaviour arose in all the calculations. For the

base case the measured initial water level was

used. The calculated system pressure decreased

significantly faster than in the experiment. The

reason was that the base case calculation had a

too low initial fluid mass. By using more

elongated spray condenser volume a realistic

droplet veloccity could be simulated. This

increased the mass content by about 16 kg. The

true initial mass of the experiment is uncertain.

The two last sensitivity calculations were

conducted to achieve better agreement in the

discharge mass flow and distribution of the flow

contributions from the two sides. None of these

calculations actually gave a better prediction

than Case B. Particularly the reduction in

prediction quality of the calculations using

smaller control volumes along one discharge flow

path (Case D) was unexpected.
STUDSVIK ENERGITEKNIK AB STUDSVIN/NP-86/109 25

1986-10-28

As for previous FIX-I calculations the

predicted dryout was delayed at the higher core

levels as a consequence of the void dependence

of the RELAP5/Mod2 dryout correlation.
!

&

STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 26

1986-10-28

REFERENCES

1. 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.

2. 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).

3. TRAC-PFI/Modl.

An Advanced Best Estimate Computer Program

for Pressurized Water Reactor

Thermal-Hydraulic Analysis.

NUREG/CR-3858.

4. RANSOM, V H and WAGNER, R J

RELAPS/MOD2 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.

5. 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-85/238, Parts 1, 2 and 3.

6. NILSSON, L et al

FIX-II - LOCA Blowdown and Pump Trip Heat

Transfer Experiments. Experimental

results from LOCA test No. 5061.

STUDSVIK/NR-84/489.

7. ERIKSSON, J

Assessment of RELAP5/Mod2, Cycle 36,

Against FIX-I Split Break Experiment

No. 3027.

STUDSVIX/NR-85/99.

8. ERIKSSON, J

Assessment of RELAP5/Mod2, Cycle 36.04,

Against FIX-I1 Split Break Experiment

No. 3051.

STUDSVIK/NP-86/108.
STUDSVIK ENERGITEKVIK AB STUDSV:K/NP-86/109 27

1986-10-28

9. NILSSON, L et al

FIX-II - LOCA Blowdown and Pump Trip Heat Transfer Experiments.

Final report for phase 3: Results of

running-in and pilot experiments. STUDSVIK/NR-84/363.
k

STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109

1986-10-28

28

Steam condensor

with steam separator

With

Fiqure 1

General view of the FIX-II facility.
C,)

0-I

C

C,)

'-4

gq

cli

'2

0

.1

~12

'C

2

'-4

'C

~1

estlet end

mooted length

m

a'

0

S

CD

part

01)

m

S.,t. ea"d

S InQA

Fiqure 2.a

Cross section of pressure vessel

and rod bundle.

Fiqure 2.b 4

Design of a fuel rod simulator.
Spray Steam 1|lets

separator

Bee. line

Conn.

tT?

z

Cin

C)j

Steam

outlet

Bypass

Conn. t

Rod bundle

Bypass

Bypass

conn. Heater

rods

Condenser

Bypass

Conn.

Test

section

Feed Water

Rec. line Inlet

Bypass

conn.

Stcam

separa' or

Rec. line

conn.

0,

0o

q%

ODJ

Co

Cl)

Ito

Figure 3.a Figure 3.b

Lower plenum and core

region.

Figure 3.c

The external

core bypass.

Steam separator and

steam condenser.

WC)i
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109

1986-10-28

31

E9 Spray water

Figure 4

Instrumentation diagram for FIX-II experiment No. 5061.
i

STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109

1986-10-28

32

ou 13 S team: -- ,relief

Steam

dome

Upper

plenum

Steam separator

Feedwater

120

Core

.bypass

Its

Guide F

tubes

8oeat k

loca tion IT

Core

Core

inlet

Zs L

127 Broken circulation

line

Break location

Fiqure 5

The nodalization diagram for FIX-I1 experiment No. 5061.
C:

C

to

.9 I CO

C Ij

@ \'-

922 1 :

F ur 6

94d

oOneo

C3

74 3 %D

149

Figure 6

Nodalization of the recirculation lines
Enq

r C:

52 a * 3-4

i t3209 62 o

C3i

33 1

,H

323

7S O6

31 aI I

to*

OH

%D

Figure 7

Nodalization of the volumes of the FIX-I1

(compare Figure 3).
STUDSVIK ENEROITEKNIK AB STUDSVIK/NP-86/109

1986-10-28

35

Table 1

The test matrix for the first FIX-II LOCA experimental

period. Test No. 3027 is one matrix No. 2 experiment.

Breek classiflcation Split break@ Cu•llotine

Trpe of simulation

(a fi Igure 13) A

Itelativ. break area (M) 10 31 40 100 150 200 ISS 200

Breeks Z.D. (ian) 6.5 12.0 15.0 21.6 26.4 30.5 16.0+ 21.6+

21.0 21.6

Inital bui•del power ("iW)

-hot channel 3.35 3.35 3.35

-everaqe 2.35 2.35 2.35 2.35 2.35 2.3S 2.3S

LO. test ld4nt. Ho. 3051 3013 3024 3031 3061 3071 3041 4011 S001 SOS1

3025 5052

3026

3027

aremi ttvn. A

SpItt break

Break twee B

SLaplirlea

guillotine

break

Break tvve C

Guillotine

break

131
STJDSVIK E.NERGITEKŽJIX AB STUDSVIK/NP-86/109

1986-10-28

Table 2.a

Evaluated measurement errors.

36

Quantity Probable Error corresponding

error to 95 % confidence

level

Pressures 0.014 M!a 0.04 MPa

Fluid temperatures l°c 20C

Cladding temperatures 1.60C 3.2°C

Small range differential

pressures

(S to 7.5 kPa) 0.13 kPa 0.3 kPa

Medium range differential

pressures

(25 to 50 kPa) 0.22 kPa 0.5 kPa

Righ range differential

pressures

(100 to 700 kPa) 0.26 kPa 0.65 k-a

Table 2.b

Errors in derived quantities.

Quantity

Mass flow rate in orifice

meter K1 (PI)

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

Probable error

0.2 kg/s

0.14 kg/s

-10 % of actual

value

-10 % of actual

value

-10 X of actual

value

I % of max value

Electric power to bundle

and bypass heaters
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 37

1986-10-28

Table 3

RELAPS/Mod 2 code features.

COMPUTATION PROCESSING FEATURES

- Several problem type and execution control options as

a. steady state Initialization 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.

CL-ASSIFICATION 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/NP-86/109 38

1986-10-28

Table 3 cont'd

HYDRODYNAMIC COMPONENENTS (Input yastematics)

- 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 whLth 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.

.NTERPHASE CONSTI-UTIVE 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 temperatur& differences
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 39

1986-10-28

Table 3 cont'd

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 heat transfer depending on flow characteristics defined

for

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

b. saturated nucleate boiling (hen)

c. subcooled nucleate boiling (modified Chen)

d. critical heat flux (Blasi 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.
!

&

STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 40

1986-10-28

Table 4

Initial conditions for test No. 5061.

Predicted

Quantity Measured Case A Case a Case C Case V

Pressure in the steam dome Impel 6.97 4.97 6.97 6.97 6.97

Power to the 36-rod bundle (mncl connections) [MVI 2.37 2.37 2.37 2.37 2.37

Power to the bypass heaters (kW) 60.4 60.4 60.4 60.4 60.4

Cooling power in the tiller body space (kW) 234. 232. 233. 233. 233.

Mass flow rate through pump P1 (kg/&) 4.74 4.74 4.74 4.74 4.74

Mass flow rate through pump P2 (kg/al 1.53 1.53 1.33 1.53 1.53

Mass flow rate in the bypass (kg/sI .67 .67 .67 .67 .67

Mass flow rate In the 36-rod bundle IWg/OI 5.60 5.60 5.60 5.60 5.60

Mamass flow rate in the spray Line (kg/al 3.35 3.35 3.35 3.35 3.3S

Masa flow rate Ln the feed water line (kg/a) 1.80 1.80 1.80 1.80 1.80

Tmpecature of water at the bundle inlet (C) 266. 269.9 269.9 269.8 269.6

Temperature of feed end spray water (C) 181. 181.8 182.5 182.4 182.6

Water level in the spray coadenser (i) .898 .897 .892 .895 .098

Rotational speed of pump P1 C/a) 23.72 24.97 24.98 23.40 24.97

Rotational speed of pump P2 C/sl 31.93 32.48 32.50 30.58 32.48

Read of pump P1 (W~e) 112.3 118.3 118.4 103.7 118.3

Table 5

List of events in test No. 5061.

Time (a)

Event Imposed System Predicted

action reaction Case A Case a Case C Case 0

The break valve V1I7 starts to open .0 .0 .0 .0 .0

Start Of cooast doa of pump P1 .0 .. 0 .0 .0

Start at power decay in the cad bundle .0 .0 .0 .0

now reversal in the and bypass Lets .0 .0 .0 .0 .0

The break valve V120 starts to open .1 .1 .1 .1 .1

The valve V103 In the broken RC. is closed .3 .3 .3 .3 .3

Start ot power decay In the bypass heaters .3 .3 .3 .3 .3

The Sly starts to open .7 .7 .7 .7 .7

tryout occurs .9 1. .5 .5 1.

The SRV is fully open 1.2-27.4 1.2- 1.2- 1.2- 1.2-

FlashLag starts in the LP (at saturstion) * 1.8 5.6 6.3 5.7 6.3

The spray flow is closed 2.2 2.2 2.2 2.2 2.2

The teed water flow is closed 2.3 2.3 2.3 2.3 2.3

Valve V104 to the evaporation cooler is closed 2.3 2.3 2.3 2.3 2.3

Cavitation in pump P1 6.5 5.8 6.7 5.4 7.3

The downcomer is depleted Of water (two-phase) 9. 7.9 9.2 8.7 6.9

Flashing starts In the bypass guide tubes volume 10.8 9.5 10.4 10.1 9.5

Core uncovery begins 23. 24. 26. 25. 23.

Test stop signal 27.3 - "

• Determined from exp. temperature curves end.from

predicted changes to positive vapor generation.

Abrevationa: LP * Lower plenum UP Upper plenum xCL ;Ree~rculation line SAV * Steam relief valve
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 41

1986-10-28

Table 6

Summary of the main results in test No. 5061.

Measured Predicted

Case A Case 3 Case C Case 0

Total time Of traniLent (breok discharge) (a) 27.8 - - -

Time to initial dryout (s) .9 1.0 .S .5 1.0

Time to beginning ot bundle uncovery (a) 23. 24. 26. 25. 23.

Drank mUoo flow I a utter the break * (kg/s) 33. 30. 31. 35. 34.

Max. break flow rate trom lower plenum (kg/s) 19. 22. 22. 24. 26.

Max. break flow rate tram the downcomer (kg/si 14. - - 14. 11.

Doame pressure at the end at test (27.4 *) (Mpa) 2.0 12.6 1.7 1.4 1.3

Max. rod dzyout tempeture (C) 460. (526.)@e 467. 463. 489. 408.

Mao. rod temersture. end of blomdown (C) 276. (431.)ee 244. 227. 227. 234.

Integrated break msa tClow (kg) 290. 256. 277. 286. 286.

Integrated steam reliet mass tflow (kg) 8. 0.6 9.1 8.6 8.4

0 Approx. at the maximu, break Clow at the test

00 Max. compared mean temperature. Moo. ot all exp. measurements put in bracaets.

Table 7

Run statistics data (Case C).

Time to) Campater

CPU time (a)

No. ot time

steps

No. ot tLme step reductions in Interval

quality extrap. mess propty. Courant

-20. -493. -220

O.e 0. 0 0 0 • 0 0

10. 322. 170 0 0 3 0 0

20. 1103. 586 32 0 16 is 149

28. 1562. 656 7 0 a 1 124

*Time ot break opening
STUDSVIK ENERGITEKN2IK AB STUDSVIK/NP-8 6 /109

1986-10-28

42

Table 8

Parameters used in the assessment comparisons for

FIX-Il No. 5061.

COPONENT €0INTINOUS PAAMETER a EXPERIMENT

(ZDENTIFIER) PREDICTION (MINOR EDIT) PLOT ZIDENTIF. PLOT EXP. CALC. NO.

CORE FLUID

MASS

NCATD

CLAD

DENSITY. 80orro see

FLOW RATE. INLET a OPT 4

SPOWER X 01a

TDEMPRATURE. LEVEL I TE I51, Ti 206.

TE 211. TE 246

* LEVEL 3 TE IC8. TV 183. Ti 243. T[ 244

SLEVEL S TV 202. TV 227. T" 232. TE 237. Ti 252

- LEVEL 7 TE 101. TV IS0. TE 114. Ti 136. Ti 171. TE 186.

Ti 196. Ti 204.

TE 210. Ti 215. Ti 220. Ti 232.

TE 24S. Ti 250.

Ti 2S9. TE 271

- LEVEL I Ti 102. Ti 137. T1 1S7. TV 172. Ti 137, Ti 197. Ti 272

- LEVEL 12 Ti 11. TI 123. Ti 128. Ti 146.

Ti 223

- LEVEL IS TE 175. Ti 190.

TE 275

TEMPERATURE TE 3

r. EtRATUR1 Ti 14

IW4[NTOAY a OPT 5 * OPT 6 .

OPT 7 * OPT 8 * OPT 9 * OPT 10 .

OPT II * OPT 12

RHO 04.01

P 33.01 - P04.01

CHTRLVAR 57

HTTEMP 4.2IOO010S

Nf'EMP 4.03000105

HTTDMP 4.04000105

HTTEMP 4.SO0OI05

TT"D 4.06000105

NTrTEV 4.07000105

NTTWMP 4.10000105

TDMPF 33.01

TE.PF 51.01

P 04.01- P 51.01 a.

RmO 31.01

P 71.03 - P 72.01 so

P 31.01 - P 32.01 .

P S1.01 - P 52.01 55

P 52.01 - P 52.02

T9EP 71.08

TDOP 52.01

P 31.01

P 52.01

WLOWJ 117

0 4

xBo0

TC I

TC 3

7rC s

R"I?

P047

Hot1?

*4T1 7

14T27

HT37

a.

U.

8.

9.

U.

U.

2

3

TC 7 HT47 B. 7

TC I MTS? B. 8

TC12 H"T7 8. 9

TCIS NT?? 1.10

T 3 TFI? 6.11

T 14 TFZ? 8.12

0 Co POC? 0.13

INLET

OUTLr`

CORE[

V[SSEL • FLUID DemStTy. boTTOP

0001IOMR MASS1 ZWWdTOm'

LOWR PLVIUM MASS IW#VT0TRY a

UPPER PLENM WASS INVENTORY *

PRESSURE LOSS. S.5. ORIFICZ

DOCOE TDIERATUR. BOTTO

UPPER PLENUM TUPERATURIE

Lawn PLENEUM PRESSURE

UPPER PLENUM PRESSURE

MASS FLOW RATE. BYPASS

gas

OPT 27 . OPT 20 .

OPT 20 . OPT 30

OP 2 * OP3 -

OP I

IP 13 * OP 14

0P is

11[ 31

PT 3

PT 4

X 602

O DO

0LP

0 UP

O 56

T 31

T IS

P 3

P 4

X602

6142?

POt.?

POUt

PCs?

TF3?

TF47

P I?

P 2?

M.117

8.14

8.15

B.16

8.17

8.11

S.1,

3.20

B.21

3.22

6.23

RECIRCULATION MASS FLOW RATE. 1. L. PUPW

LIN•E (ORIFICE K)

MASS FLOW RATE. I. L. PUMP

(ORIFICt K22

MASS FLOW RATE. 6. L. VESSEL INLET CSPOOL PIECE KIOl

x 602

X 604

I £10

"00

X 607

a"e

WLOWJ 201.02

WLOWJ 202.02

WFLOWJ 97.02

Th'ASS

MPLOKJ 404

CNTALVAA 53

X603 MF2? 8.24

X604 WF3?7 3.25

XG10 MF4? 3.26

MAT? 8.27

X507 MAS? 8.28

HLI7 8. 3

. SYSTEM MASS INVENTORY

MASS FLOW RATE. STEAM RELIEF

HEAT OISS. PASSIV[S
STUDSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109

1986-10-28

43

Table 8 cont'd

CN(PNT CONTINOUS PARAWTtR e EXPER lMENT

(IDENTIFIER)

PREIOZCTION

(MINOR EDIT)

PLOT WD[NTIF. PLOT

ExP. CALC. NO.

FLUID ODNSTry

MASS FIL.OW RATE TO T2

MASS FLOW RATE TO T3

MASS FLOW RATE. INTICA.

MAsS FLOW RATE. ZNTEGR.

ZNLET TIDACRATURE

INLET SUSCOOLIN

T2

T3

X 639

e*a

TI 34

ase

PT S

me k.o

WFLOWJ I12

WLOWJ 151

CXTRLVAR 95

CNTRLVAfR 9O

TD0PF 26.01

TEMAC 90.01- .rC~f 51.01

p 96.01

00437

X636 MAO?

T 34 TFS?

TSU?

P 6 P 3?

8.29

8.30

3.31

5.32

9.33

8.34

8.3S

INLET PRESSURE 8.3r,

RELAPL.IE02 CMMTAtON CPU TIME

COMPTATION W ASS ERRJl

see

*so

C€ITIUE

VDMSS

CPU? 8.37

AE7? v..u

0 T[ CWAtSOK PAMA"TIRS Ait TOI"E REPOR•TI AS OIRECTLY WASUREO OR AS COMPJTED RESULTS FROM THE EXPE[IMENT.

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

es CORRE CTIONSAPPIED TO RESUME THE CORRECT PRESSURE SENSOR LEVELS.

one NO DATA AVAILASEL FROM THE EXPER.I&NT.
k
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'.i

X101-81030 " 28 0. 0. 0. .1100 4118*14 11000o100

.11"1M M1040 101on a010

.6O0 o 1180.84 1080.0100

.3*111 1Ili 11003006

.3115 "Mat 1100 I00100 3.40130 11l0.1 131000100

.14000 111184 13I000100

.03I4I n164 is800000

.lot)I 18011 111000100

.314 "T Ml0880 110004109

.1310 1I110.ow )14400•100 .30303 M1l'0 110000100

.k11 1I m 100000010048

.151143 1,1PO.R 1100mm00

.30114 141F.4 o10000100 .80330 11104 8110•O 0010

.30130 M184" 110000,40

.30330 "1P1040 810000100e

.8-110314009 " ^ oWO1 0. 

0

0. .30314 111014 ' to0lI 1" 

.1)590 I110 I0 OooI001t0

.10418 HI088 113000100 .613005 118040 lo08o00060

Was :1101 a 38010000100

.31040 1 We"1186 800 

0

a .1.00332 00"ml 50000100

.01100 1100 4110000

.430311""4 0010060013 .4010011 0880H 0400,O0030

.•00001 1"0 010000100 . 6000 11114 619000100 -. 33388 1104• 3110O00101

o. II4II 118088 111I0¢0016

-.4IO0T Sm I 4 1110001. 

1

.1•00 I1040 1016000

Il~l AIIll I|OQ

0I.11-m11031 30 0. I 0. 

0

0. .60103 1114 040001 

0

.1500000 |08 9000

bo.43900 541818 90060

.)4ASO .303il 11818 113088 900000800 10100100

.01300 1110860 •093000

10141 16.4 I. 0. 0. 0. 4. C86141VA 10

I. ¢HlPIVAN 0I

I. CUI11LVANI 13

91A.1-1311 INIICIAI 6. 0. 

S

Il8IT0LVA0 10OO€

001.-1103 11l01t I. 0. 

0

0. .610 #1111 400000800

10101101 01001001 .

.6150 II0 118084 111088

01011504 .6150 11818

101101 .660 Is O 08

M010508S .110 138

0105100 .1A0 0110.0

10101109 .I30 I111040 30100sa0 .610 k1108

30101100 C- 0.OI Itdl.4iam 3010S1l 11T4[ 0 001

3lOo00 a WPAh.SSPow 11•*8(110

30103100 884E 0 003

IOSO1 O0 101-o80 30 0.

20.01,01 0. 1. C"HIt 

V

30103903 I. C.61 IVA

0105"000 001MC.1001 611140064 01004006 &W0"J 8 0000000

*.88.0808l 8IN11844 VAIK4

0316"a S 1041110. 141.64

0310100 ' 0311410. I 41.60

01600 4901100. -.:$IF

0130100 1 1310000. 8.0

0o10300 1 1001330. I04.3?

0110100 3 3066)00. 043.36

0310100 2 10111)0. s19.01

01,40100 1011150. 041 .4 01o0oo 1 01.1 1:. 61 Is1

0940100 3 111310. 400.

0910310 2 1018110. 941.80

0100200 1 1043610. 400. 2010100 3 , 01 call*::. 3010100 3 ' 033080. 4A 

. 3030800 9 1041100O. 143.81

13010 3 303080. 040.10 00862I03 30310. 01.0000

0041203 3038610. 0.019931

0041101 3089210. 0.010151

0046301 3 015110. 0.010033 0046300 301 010iD. 0.001111

0046101 1001100. 0.099804

0003 3 1003420. 0.6 24 

0

0046300, 3 09400 0.63646

0041110 Si083010 0.64640

0511601 990440. 0.034111

01s 0 01 0036140. 0.'1401

0~6660l 01T3090. 0.10101

0636061 4110100. 0.1130

0311101 3 0941990. p.111s4

0311101 1 116410 0 )3096 0211103 4981040. 0.013110

01103 2 G1180. 00

0111104 1a 1110. 141.14

0166306 1 l100. 843.40

0463061 3051100. 143.03

0441 01 3 101t910. 143.1,

400000100 400004100w

900000400

4000OOOO

400000100 4O08100030

=0000006003

400001000

8. 0. 

0

I. 0. 

0

0. 

0 I0 01

I. 0. 

0

1-4

tD

00

M'

3D

O. 0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0. 0

0.

0.

0.

0.

0.

0.

0.

0.

0. 0.

0.

0.

O.

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0..

0.

0.

0.

0..

0.

0.

0.

0.

0.

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0.

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61-4

100

0%

OD

W0
I le/I Ioc llSO Si) oo0 . 0 0 5

04le I0 I "$"s M10.10 o . 0. 0. I IIII)0 I 3 a. 50 $I46 666 10 0. 0. . 5

goa .A41.. I6A&yIg

0416)0I 1.600 3.061 0. I 31.604 I.III 0. 

011,6 4 ,14 4 615 W.441 0. 0 4.a1 0. 0

004160% 4.6 £.66I 0. 0

06I)0 I

N: lo"I 0.600 111 0. I

alsoI06 -I.14 .6l 0. 1

0i166I1 I 0)16l0l 0.01 0. 0. 5 4111116 I

036)0 66.43 0. 0 01l1)0I 4.54| 0. 0. 4

01416)0 I o~llow l

"at6)06 0.05 0. 0. 1

11M m

Wn

Transient Input, Case A

* IlU-ll 60l0 U 1A3M~l) S~ ll .9011. CAM it,090.1 so("4 0,1914,41 6161100 #"$11 e 100 I S011101 Mt I 161Sl GA 

000060 b' U DIwI:l "OS C005 401 Is.

0000306 as) 1.04.0 .003 0000 60w 60f lo 11

.10

* tal~eeoooee

0000 1/6|1t

610OII l~ t "al. 0 0. q. all(fv %east

"W

* i 100%

0%

IN.

0
S I-4 I,.eul I04 to1AP$AM0i 0 In. 31 OCUilOt i.4 ONSAN OtSMAi416 1 0NO. S1041 * 10 $ II gll•IM 4031I emaill *e I $l 0. 1l |IiaI :" II A I6* I6I

CASE0 S. I SIDT.1 Will

000010 iM s

00do0g0 I0. . 0 . 0000101 IS. I o04.6 .0615 3000, 0 400 400

Steady state input, Case B

gililOg .4.466 6.iSS 0 * (00

$

"1041I9 0 CC MALO 3.

V oii AMD %tit MAN 4.0 $llAS 106•e4 t0o mae I6k11

0

Ol OOOI I

O6III0 00 1

0ll000 i

V o""aI a.O I

giI.,., 1gig I .014 0 lloff 1 0.0 1

s1olo 4oI

g11i0441 0. 0. 1

T 00016 00 I 0I 3 eou,,ei iCM 6ooeoo

1.1": 811. *'~ . :11oo0Cee0 V. . .....,, .. * ......... :t.

000000 JUNIS-1I 1•00A5 1000101 011000006 11110141 0. O. 0.

OtOIgl I a.460 !111 C.

4010000 IlCAim" IMII A , 4I010OI I * ...... af0 0.3

40:1000 1 0 CmlO.VAA 04g "Slo,* 1.6 -I. .01 0. 4010101 1. I. .01 0.

. 116.640, @16661y P04 Way0.16 900

06330 It 09306350. e.*oa e 0 0111101 1 0i0I401. 5ll6000 . 0. 0. 3 :813 00 0l3l)00 6 IH0 ,l00 I , I

.1• fil SIAIC

a)

I-.. '(O4 <

0 ,

03

IN

I-&

0

x

"H

0

H
Steady state input, Case C

* Ill-Il 0061Mot33 14 set" e 11 33t13 - 10a6Sa

o100 Set 3 I I 61 It 1l:64:5 S CA C. 6f110*11 0j00 C.AM 0 S3600V S3*

%D01 of$IAA0 11101-$1

0 e41l 1:1 11O00103 30. 10!.

000010 30. 1.69-0 .0416 Spac0s I6 lo6 1000

e f eltll

60004Sao 1-4 6 NAIL W 0 II. t S1I(4ed 0I151

...... 3......... ..

lO~l0OS *.l0O s. *.,0l0l 0. 14.4 O.916 0 3060300i 010031000 *.00411 0..1 c.oI 0000 1030360 0I00 I0.00441 .0 .0 6i33

31001100 10410160. 661.46 3030333 3 4.16 0. 0. 3010303 3 4.34 0. 0.

3036301 303.0 0 1o1.40e a o.600 0 V. 0 0.O016 0.19 0o.I 6. 0.1. 3. 3O006 :30001 0. 01 . 0. 0. 0.

! 01r W01OA i 5Ori 04. D6AL01•010,11111 FLAMM ASIAJa0(L 00004 0

: .10019 631050.A3mk 3A041(tyCOS( I 04115 felt oleo MR4506mo love * 030(3A3 ID 0 3 4 03*4*1.6.

feo" 01041.11RIAlIl ifieldAI FOR1100 bit DNLAIA ANl CILU40.

3033I06 3

0IIII0I ..I3,I,•4 0.1,41.4,01 .

301:110 3 4

030 I 04.3 I 0..1.0.00 0.60.0. 1, .00.1.0.

263)1: 3.0.00..90

141110o I a

166360O0 0 4

to# Ise4 I I

36119 I$O 61..

3033603 0.001.0.11 .0 111

3033103 .6.0.1. I lO 13 -.0.43.1.1 -0.00, .3. -0.66.3.66

30101AS -,0.,1.10 I *.1. . . 6 0

30133000 3

30361 1.3.3.36 4111011 41.4....14

*~ 360 9.60 MoIltI I

10100 IS 0.0.0.01 4I1.09.9.0. 0.104.0.1 0.060 1033300 0 3033303 6.0.0.0 0.3I.0.6 0.I3.0. 0.34.0.0 0.2.0.94 0.4.0.10 300333030!..6.0. 1 0.6.0 0.0.6.0 0.96.0.0 6.60.0 0

* 15r00.3 I036130lllll(3C 304 065 64*e l314l1L666 10333300 3 6 103 111.10.110 0-0..11.1 0 1.1 , 4 11.11.31 6 I.,1 of 0 .6.6 So 1 .1 ll.413360 0 0. .6. 6.I 4,61,4.4 I I.0 &1

melI• I I

3033360 3 1 3633.363 .3163.160 31.31134, -00..1-.- 0 .0.0.-l 30II3II -0,.0-II0 -.0,-1,.0 .*t0.• -1,- -,,0 .*. -I 00-.I.0 lattice- .i -4.4 a -41.6••-IIIII-III ,I 3034300rlAIL~r .6.6.3.36 .0.0o1 43.41.66,II

PHA 6 I erO A. a I034O3 "1.0...000.19.. 0...6 .03.063 00 gas011 I. 6 I 104 0 I- a 3.1go.It1 00.9.00 0 3l6310 4 0 ..46l . l. o I

1016000 100 1 1 0los 0.s 0.0G.0. 0.6 0.36.0.306 0.00 100111 0.1,.11 to.0 6.0.0.. 1 30 00.3.0 3031000 0 3

103633 -360.0. 01 -01. -t.3 . 1. 6I -41.4t.10.1166 3033363 -0.11.3.6: 1-I.3s.. -1..3.0. ... 0o

1036300 6 4:0tvi00

3033360 -3.0.4~.13 -6. 6.1.10 .i.00,1.21 -6.431,.04

1030363 *O0.li3.3i 1,00,.3.0

"0ells6 0. 0. 3000. 3oo0.

1031*116 a656 0.300 Is,033 0. 30 660000 0. 13 0.116 0 6 3O01030. 06403600 063 6l .10 0.36 0000

31lo0t 9314000011 0.000160 .0 .0 6il3 3030306 I 1o01t36. 463.13 1030303 0 6.61l 0. 0.

1036303 3 6.01 i. 0. 30103031 0 0 -6 -3 0 0 0 3030101 101.66 II0.43 0.03036 3. 33.1 3.

3013061 0. 0. 0. 6. 0.

3011000 3 6

10336 0.0 :6.30 6.3 S.) 0. 3.601o

30111310 1 1

3010133 0.0 0.61 3.0 3.60 10O I a

10311313 0.0 ,-.60 0.3 -0.106 0.4 .0.-0 1.1 -0.001 3033tes I0, 0.I'6 S .0 0.646 3.0 6.000

1031300 3 I

"totagl 0.*..80 -0.1 . -0.33 0.01 0.4 

1oll03 0 0 3.0 3.00

1013100 3 1 1:I1363 -.. 00..Go -0.66.3.03 -0...6 -0. 10.410.1111 1013301 0.00.3.0it 3~03300 3 4 1013303 -i.00.6 00 -0.16.3.I1 -0.63.3.36 -I 1006,11

103"363 0.4.0. .1 10131301 0 1

30 11330. .0 .10 .0 -0.0 . .

3033333 O100< 1 1.. 0.11.3.3 -6.30.0 0 0.401..14

3010333 0 3033063 0.0 6.60 6.106.00 6.3 0.06 0.3 0.06 0.4 6."0 0.6 00

in

N

M)

?54

3033300 I1013006 6 006 01000e 00000 0.0010 0.0600 10111031 .:.0

IOll I : = 1O• :" : ::•O •O:." •• 41 Of O .0 #%%VS~ 14CA tIO oSICADV Stlf ll 0

1OilI00 ttoll . #410o).

10ll , I, I01 IO .

3633631 06.01 6330 0036036.410030 604

3 10330 066030.006300

iinI00D

0~

RD
Steady state Input, Case 

D

tnW

* u~sa-fs000021 041i4l 4 0e(IIAQIst illl 010 20033

o 200 1 Split 0004 A 00l 116011

I CAl 0. *110000 q CAM Am a 115*O0 SI0l*

0000101 Is= 011 0.I4I 11 slII s 0000 00 ow1 .0001061 I0. 00.

0 too001 10. 0.01.* ."Is 0010 00 I 00O 0000

:110000 VOLII 5 Am 

i

41118001 -80'0

cooII . I

lo~il t0O":lllI gl I .P

101O=1 l.49ll1 I toll 10ll II11

041000:1 140001

:ll: , V04. 1 0201101 0.. I

1101,01 0200401 4.01000 .0. 0. 0.10 0.10 a 0.26 0. Is .0 

oilt It tllitll

t1000 "10. 10.100 .

...0111 0. 0... 0.

I0000l votes 0 K

0111401 sa -0.1 1

NlsO 0.00 I0.. 0I 1

020300 0.0 I5.

el 00e 1 .0 0 .

01010) NIS, 11 100014

0I10401 0. -.

0160001 .. 1 I

II0,001 0.0.I0II ..... 0000 01i01010 .0011 0

031i00 1l II.

0I010)0 0.I011 1

II001I0 0.00 1.0 

1

01110001 04. 2

0010040 0.00 0.0

0111o041 0000N 0 I*

00000010 01os

I041001 0. 0. 

1

014101: 1.00 

0 00110 Do 00

.a" 

I tI I"

"20) 0o 000 .1,

111311181 41.00s 0 0000 a 0.01 1

l1l0)i1 .0 i

111f001 I4O. 4

isI10 lissome00 0100040 I 1 .II0I 

4

3II03: .1 0 "00s I .010I 

4 02I120201 0 .0 .0 0 4

111301 • .0 .1 .0 

. a .

NII 449se ",611 so" I 1 .011 12114"l0 1.11 1 " .0 I m.s0 a

12119601 0 0.01 • 0 0.400 a 0.00 

1

M4100200

121"0.00 0. I0

I1I00I

02I•0.08 I00 0 04

11"1008 ll0100 0 II0000 .020I I ol2i

I*'@'20 so 21 1 1 

0 1110to01 .0 3 I

11.0040019 0.

0lo00•o0 * S 1000 0I Il .I

01916010 200000 0100 0i 0000

.020002l 0 .0 .0 .0 00 iiiooloi 0 .0 .0 .0 i6

0A2SOOO 9 1 1 6 .0300

1 010106 0 

1

12601001 1 .0)0I

II"MIoio I,

1900000

0 "00I N 0. 0 00100101 01000080 i*0€o I I .040i 

2

110000400 .0), 000 00

10liO100 0 .0 .0 .0 

a 10100100 0 .0 .0 .0 2

00400000 0 2 1 0 .0)40

00400200 0 I

00000001 2 .0440

I10400201 .0 2

00400101 0400001 O I00• 0 I .4022 

2

10400401 0 0 0 I .400) 

2

16048020 0 0. 0. 0. 

2

01400001 0 O0 0. 0.

02I0I01 1 00l21l0. 0.24)60 0. 0. 0. 

0

II21I201 2 6002000. 0.02206 0. 0. 0. 

2

0211I2021 600020~0. 0.0 I. 0. 0. 

0

:11112104

0011100201

0300301

0else02

004120O

01I1)01

00I0200

00II1)01

0111.

222S2221I22

0 62

00.4

0.4)

00

I001040.

6904000.

9600000.

4 (0100$O

6001010.

2001160.

Mo40100.

1011160.

2 0.

0 .

0.

03. ;0

641.01

14, .4

400.

0. 0

0.

0I.

0.

0.

0I.

0.

0.

0.

0.

0.

0I.

00

I,

04

06

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0. 00

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In

to

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sO
STUDSVIK ENERGITEKNI-K AB

APPENDIX B

Data comparison plots

STUDSVIK/NP 86/109 Appendix B.1(21)

PLOT IDEVT. QUANTITY (EXPERIMENT)

NO. (CALCULATIONS)

5.1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

MHI?

a. 2 D 4

B. 3 x801

NFL?

Hi"?

3. 4 TC1

371?

a. 5 "C3

1. 6 TC 5

m17?

a. 7 TC 7

IcT4?

aI. a TC 9

a. 9 =C2

5.10 7ICI5

1.11 T 3

Tn7?

5.12 T 14

T727

3.13 D CO

5.14

5.15 D DC

mO?

5.13 D LP

5.17 0 Up

YOU?

5.13 0 53

PDS?

5.19 T 31

T23?

FLUID DENSITY. CORE BOTTOM (RHO 04012 CASE ?

DIF. PRESSURE. CORI INLE.T RESTRICTIOH (DPT 4) * IXPEIMENT

DIFF PRESSURE. CORE IN.LET RESTRICTION (P 3301 F P 401) CASE ?

rLECTRIC POWER. CORE - EXPIMENT

CORE HEATING POWER (CHTLVAR 5?1 CASE ?

MEAT LOSS FRCOM PASSIVES (orTRLVAR 531 CASE 7

1Ai( CMAD TEMP. . LV= 1 (1191 T206 7211 T246) t .l/D

PIAN CLAD TDEIgATARt. LEVM 1 (rTTDZ 401000105) CASE ?

MEUAN CAD TDE.. . LE 3 (T10 T'183 T243 T248) * EPIMENT

PMAK CLAD TO•MERATUR1. LEVEL 3 (Xr3TZU 4030001051 CASE ?

€RA CLAD " TDm.. LEV4L 5 (T202 7227 7232 T237 T.53) - PERIM=T

PMAN C.AD TEMPERATURE. LEV 5 (MTTIDqP 404000105) CASE 7

WI CL.AD TED•.. LEV'L 7 IT101 TO 7271. 13 IODS) - EXPERIMENT

MAN CLAD DDI7ATUIRU. LIVEL S (NT7DP 405000105) CALSE ?

MEAN CLAD TEMP.. LEVEL 9 (T702 7137 T71? .172 T137 T197 "2721 - EXPEIMENT

IAC.AD 7ATEMPERATURE. LEVEL 9 (CTTZMP 406000105) CASE 7

HAM CLAD TD[•.. LEVEL 12 (TI T"123 T128 T140 72223 - EXPERIMENT

PEAlS MAD TIDIERA7TU. LEVEL 12 1TTDW 408000105) CASE ?

MEAN CLAD TDCP.. LEVEL 15 (T717 7290 T275) * 2S]EIMENT

REAN CMAD TEIDESATURZ. LEM 15 (W•"T 410000105) CASE ?

Pr OlD TZD•[OATURE. CORE IN=LT (71 3) - ESPESI

FLUID ZVOCRATURI. C=RE IE (TER" 3301) CASE ?

n=D TIWITRATURE. CORE CUOALT= (TZ 14) * WDIIT

aIzD Tz•A=TUR. CORE OT (TDar, 5101) CASE ?

0177. P• SURE. CORE (DPT S * OFT 6 . .... * OPT 12) - EIPU•I, I

011 PRESSURE. CORE (ItOM P 401 - P 5101) CASE 7

. . . . . . . . . .

FL.U1 ID OSITr. VESSEL BOrOM (311O 3101) CASE ?

DIFF. PRZSSURE. D 6COM (OPT 27 * .... * OTT 30) - I[PUIRDIT

D011 PRZStS•U. D0OWNIC (FROM P 7103 - P 72011 CASE ?

"1.7. PssURE. LowMES Pm (OPT 2 * OPT 3 - OPT 1) - WEXIMINT

bl117 PRESSUR. LOi PLENUM (FROM P 3101 - P 33011 CASE ?

OUT7. PRUSSURZ. UPPER FLUOM (On 123 * OnT 14) - ZZUI[•MIM

CITY PRESSURE. UPIES PLEMM (FROM P 5101 - P 5201) CASE ?

0177. PRISSURZ. STEAM S1ARATOR OCRITICZ (O•T S5) - 137 KMI0r

DI•? PRUSSURE. STEAM SPARATOI ORIFCE (P 53201 - P 52021 CASE ?

lrflx TI•IRSATURE. DOWN C 3RCIACH (719 312 - EXPERIMENT

F.UID TEMPIEATURE. DOWWCOMM BOTTOM (TDMPF 7108) CASE ?
i

STUDSVIK EYERGITEKNIK AB STUDSVIK/NP-86/109 Appendix B'.2(21)

1986-10-28

PLOT ODENT. QUANI4TY (EXPERIMENT)

N0. (CALCULATIONS$

5.20 T 15 FLUID TEMPERATURE. UPPER PLENUM (TV 15) -* EPERIMENT

T74?

5.21 P 3

P I?

8.22 P 4

P 2?

B.23 X602

3.24 1603

M72? 2.23 X604

5.26 2510

"Fr4?

5.27 -

MAT?

&..I$ X407

PWS?

3.29 ----

323?

3.30 X&36

MFG 7

3.31 ----

3.32 X671

3.33

IM.2?

3.34 T 34

3.3S ....

TSU?

5.36 P 6

V 3?

FLUID TIPERTUP.E. UPPER PLEN•I IL |JPF 52011 CASE ?

PRESSURE. LOWER PLJDIU (PT 3) * EXPERIME•T

PRESSIU L0WER PLENUM (P 3101) CASE ?

i"iSSURE. U7PPE PLENUM (Pn 4) -EPEIMENlT

PRESSURE. UPPER PLEDUM (P 5201) CASE ?

MASS FLOW RATE. BYPASS - EXPERIMENT

PASS now RATE. BYPASS (,rLOvJ 117) CASE ?

PASS FLOW RATE. Z.L. PUMP - EX.PERIMNT

MASS FLOW RATE. I.L. PUMP (PLDWJ 20102) CASE 7

MASS FLOW RATE. B.L. PUMP - EXPRIMENT

MASS FLOW RATE. i.L. PUMP (LOUJ 20202) CALSE ?

PASS FLOW RATE. I.L. VESSEL. ILET (SPOOL PZIC KI2O) - E RIMIENT

MASS FLOW RATE. B.L. VESSEL INLET (IMLOWJ 1901) CASE ?

. . . . . . . . . .

TOTAL MASS. IN SYSTEM CASE 7

MASS FLOW RATE. STErM .3tEF - EXPERIMENT

PASS FLOW RATE. STErM .RZL. (K@LOWJ 404) CASE ?

7LUID DEISITT. ZXZAM (R3O 9601) CASE ?

MASS FLOW RATE. BREAK FROM T2 INVDETORY - ZVEnItI"NT

MASS FLOW RATE. ZREAM (Pr1.WJ 152) CASE ?

. . . . . . . . . .

MASS FLOW RATE. IREAM (ILOWUJ 151) CASE ?

MASS LOSS. Ir.AX FLOW R.ChERV T2 * EXWPD ET

BRZAX TOTAL MASS LOSS (01TRLVAR 55) CASE ?

WREAM -. TAL MASS LOSS (orTLVAlt 60) CASE ?

FLUzD TDu=ATvUR. sRum INLET (TE 34) - ESrfIpwd?

FLUID TEMPIDTURE. KUAM INLET (TEMPT 9601) CASE ?

. . . . . . . . . .

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STUDSVIK ENEROITEKNIK AB STUDSVIK/NP-86/109 Appendix B.3(21)

1986-10-28

• •.UIO OERSITI. CORE lOuDn IR0 0401I CASE A 0 FLU.O OERS3??. COME 4O?,C IRO 2 c4:*, CASE I A , LUIO ....|T.. COE SOTIS. IRMO 04011 CASE C 4 PLU1O 01SI1T. CC OE 10O IfteC 0401) CASE 0

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1986-10-28

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1986-10-28

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1986-10-28

1 REA:m CLAD 1C19. Ltv EL 7 (1101 10 EX.P~fOS)*LCRIP(

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1986-10-28

a PIA: CL ADlfp. LEVEL 2VCCI? 11 I1222 11280 114, I'll, I'llP o MEAN CLAD tE~lEAUE CR2 LFE IMIIEO 407015 CASE A

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1986-10-28

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1986-10-28

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1986-10-28

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STUDMSVIK ENERGITEKNIK AB STUDSVIK/NP-86/109 Appendix B.11(21)

1986-10-28

o 011 USSUC. PEX PLCMU~ 110pI 13 ;J 1P 11 - EIPCRInCm? O III .tIRCI~tJC f: LPEI~WUMM FROM F PI£0 P $203, CASE A a Corr il SSJI UPPER PILCgUM It3DM P 31001 *P2011 CAE I 0* OIL''ft"SUMt. uP'R PLE mU 1cm P£0 * P 20 CASEC X Diff PRESSVOC. L*PEJI PLENUM 111OR~ P 3101 P 12011 CASE a

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a 01 FF. P'tssi*(. sttARq SEPNAIA~tom R FCait too? Sao * itl a Dirt Plots~u v31C SAMIPADI aP 12 03 32 021 C & 013 PCSSV3C. S11:" SIPARAIOM 03 rc 1'C 122011* P 31023 C

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S=tJSVIX ENERGITEEKIX AB STUSVIK/NP-86/3109 Appendix B..12(2:.)

1986-10-28

0 FL.UID ttPrfeAIUftt. DOWN CO0EIS 9:??0m Ift III - EXPERIMENTE 0 IU I ID t 11 1 1 1: DO COýwCO-f I0O?'C 11Prn 1`10411 CASE A a rLUSO It pt .. , U: EC. OWMNC2"( OTO19" CIEtr ?1061 CAt S I + FLUID I~efP*(AIIUmt OOWNCC(ER I037CM t ?EIVF ?1081 CASE C X FLU 1 0 IC3PVRA I UR. DODWCOMER 20flOM I~TEIP ?SOSS CASE C

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1986-10-28

fi PetlSUNC. LOWER P~t~tNt VAI) Czlffitisrof g PCSIUR c 0t PL VM 11' 3305) CASE I

* P1S~uIV 10101, E:1 1 3,100) CASE C x PSSU E LO E LZUm (P 305 CASE 0

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1986-10-28

RAS$ FLOW A. YAS*£PW tN PIASS 'Lo0w aAAt. BYPASS 34t.WLOJ 133,3 CASE A RASS 3LOW ATS I IASS -~.W 0 3It CASt I MASS rL .0 BS. A 3E?,A ,S W , .C~J ""7 CASE C

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1986-10-28

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1986-10-28

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1986-10-28

O FLUI0 09NSI 1. EA1AK :."0 5(022 CASE A

a FLUIO ESfTI. I(SAA 16O 60 1) CASE I 4 F L U ID OE NS II T , I5 CEA IR MO 9 60 1) C A SE C * FLUID DEES|IT. IDEAS IA•O 1(01) CASE 0

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1986-10-28

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1986-10-28

S V S SlE tE 9:1g'OA ASS LOSS ,ICVIA OT AS A

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STUDSVIK EENRGITEKNIK AB STUDSVIX/NP-86/109 Appendix B;20(21)

1986-10-28

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1986-10-28

o PU? IME CASE C

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STtJDSVIK ENERGITE1KNIK AB STUDSVIN/NP-86/109 Appendix C.1(4)

1986-10-28

APPENDIX C

Calculations to experiment data uncertainties

Case A CAI.CU6.A (04..7-IRM•lIN0 -? DATA 6J6Ct1QTlj4 ANALYSIS F 04o6C/ICAD.

pf5T? L.11U @051MP444e 4I1I•I54846 -LCSLAT7O NM 4AVIMGOI) U488111W4L DATA AT tw 4O1f 4 ZIGTIIVAL

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20.2 24.4 34.3 33.0

668 - TICS as.3 125.4

24.0 a 17.1 34.2 •1.1,

W • - TC11 23.2 44.A 2•.3 44.7 33.4 44.3

SI17A * Ms1 -. •001-01 -4.31 ( .44 -3.43

ULIA - MIS .4.44 -10.1 14.2 .7.10

20.0 7.96

-. 323

.. 1,41

71-4

3.424

3.23

1.43 -2.77

1.47

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,1441-.01

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3.40

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-6.13

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3.31

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0.74.

-41.0

-- 4.4

-44.2

41*1

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3.36

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43.0

432.0

-3.13

4*. 24'

-64.6

-1.41

-64.4

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-. 234

.19%

.119 .IOl

.541

I 7O 3.10

3.50

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.a lt

3134

-. 672

.641

-. 3340

-3.41

2.041

3.34

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3.619

-.480

.531

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3.37

.341

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3.14

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00.17

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5.20

- .440

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.173

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MS.S

1.30

3I.43

11.4 S

74.0

3|4.6

34.07

3,.4

(4NI.4

-67.3

44.3

37.14,

241.1

43.3

1.20.

20.32

2)0.2

-.77 -.24 -. :242 -.27 .243 .294

-. 2%2 -. 336 .. 217 -. 211

.231 .211

.A36 .231

.146 .404

4.94 1.37 4.57 4.51

.441.01 .I4S .2431-02 .111

.1311-OS .548

-. 424 -3,21

-. 103 -l.48

3.14 2.01

-. 267 -. 102 * .441 .8T22-01

.131 ,27s

.o12-0*l .39l .4472-05 .200

1.17 ,341

1.24 -. 0W .alt-of .315 1.41 .32

,.4,4 .541

,373 ,.244

-:.11 -. 236

" 41 -6.33

.741 1.41

-2.04 .4.49 .3.S -3.47 3.44 3.44

.5441-03 -. 121-C01 .40!4-02 -. 2701-02

.64111-02 .I32-02

*.3•4

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.132

1 70

TAS

117,

.447

.214

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1.42

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- .1071.03

".14411-0

.1411-01

6.31 7.44 7.44 i4.7 ..15 7.11 4.4 ? 17.4 7.13

-. 793 -. 442 W!.5 -.,I4 -.123 -. 211 .434 ,111 1.3,

-2.04 -4.11 -a.$# .:I13 -3.8 -4.24 .171 2.73 a.37

-3.S4 -4.44 -60.4 -S.:7 -4.44 -?.14 3.24 4.14 7.64

-2.74 -4.4l .4.15 .I.3 -3.*11 -4.44 1.77 ,3.1 7.04

-4.40 -13.2 .68.6 -7.24 *6(.I -61.7 7.34 16.3 l1.4

-4., .4.40 -,1.6

,4.01 -1..3 -11.4 4.:4 7.27 12.2

-00.1 .- 4.1 -21.,

-log. -44.I -14., I01. 93.S 11.3

-.04. -68.2 -42.2 -03.8 -71.0 -"4.3 119.2 73.1 19.5

30.0 -6.64 3.03

44.2 27.4 4.44

4T.0 .346. 2 6.4 112. 2.04 -21.7 43.7 31.0 22.1

2.12 .40 :-32. 40.4 .471, -24.4 13.2 13.0 21.1

3.01 -*.3 -4.7 43.3 o.f.0 -4.46

44. 1 3.224 41s5

-2.46 -4.72 .636, -M410 .-.41 -.7.4 1.A 3.53 1114

-3.3 -24.0 -24.4 -22. 4.1 -27.3 23. 24.4, 27.3

-.9071-02 -.2371-02 -.5(21-02 -. 3161-32 .2L71-02 -.5361-02 .23L4-02 .$411t-0 .24s1-02

OWIA - 1405 .62211-05 -3611-41, -.7131-42 -. 746C-42

.71-02 .3621-02 -.3351-02 .3243-02
II

II

STUflSVIK MTERGITEEM1IK AB STIJDSVIX/NP-86/109 Appendix C.2(4)

1986-10-28

Case B

O~l.ULA ~0tO.18f6~NtOATA LDkC2Ttt4:'rv ANALYSIS ?OR *RVCJIAP.

FIRST LINE D681610001 BETWE1N CALCULATtO AM £V8GO 1A1RC D) EVC 0t&NA&. OATA ATth2 OF til Io4ICRVAi Sir~dO0 61, o EA 1 Oluat P.6 "CE OVER1 ?m( ZI*IVAI. IN:PO LINE ULAN SIGM OVER TH4, INTER6VAL (800? MLA0 3LASSd OF ThE 05'ZIM49MCS

0*1.C. 118. 0.0 - 2.000

0168 2 -. 2129-01

.19141.02

.46010

* 26 * 6 6 .1661-01 22-0 .0 

• is * 6 .$So .139

P0ac - 0 O .1.20 * 71.5

IN.1

POIG - 0 LP .1.2. .1.16

0.34.

800I -0€0 .. 721 4.,'

:1.0

POR - 0 U, .1041 .5741-01

.502

8006 o 0 00 .1410

3.02

M - 0 $6 -. 402

4.17

win * 1602 .1221-01

.312

.:"4

Win - A503 -. 113

,:31.1 1.25

I120 - RA0M 6.36 3.31

2.22:[O 4.0'

M516 - FR1401 .704.0

.2=9-01

T496- 1610 .2.02

-. 27

4.65

W168 - T143 -02.2

-.06.

IN&

?FIG - 1 3 2.01

6.77

EI.; -6.06

7626.16 11.:

TY21 - C 31 2.2.

01 ,S

2.52

?Via• - ?€ 34 -41.

-41.

].56

176:8

"?•Il - TC 1 40.10

tG - ?C 36 14.1.

2S.•

3.46.

HIS* -TC 7 71.6

211.

NTH - 7U 1 46.10

.0.36

.3-0 26.

2.54

ff~l - -I2 7.26

tO 7 1 0.

06.1

KT79 - ?C2S.34

5766 * 10 2 20.

2:13

0tol - t~oll .6260-

2. 7312,1

. Tug INTERVAL -. -

- A.0 * 7.000 - 10.00' - 16.00 - 20.00 * 27.00

.. 1113101 -.,701o02 -. 6971-01 .6271.01 -. 6921-0T -.1&$ S.1011-01 0,171-01 -*4581-00 .171|*01 .6741-02 -. 123 .26811-01 .0861-02 .I141-00 .5121-01 .811-101 .1227

•212:-02 .1111-01 -. 401.-1 .J391-01 -,6711-00 -. 117

.2?:1-02 .2011.01 -. t11SI-0 .4236101 .2:61*02 *,201 .2111-01 .a111-02 .11- , - a .S1 .7- c 0

.740 .114 .II9 .J22 .443 .200

.725 .737 .723 .621 .11 .341 .722 .721 .777 .112 .16" .365

-1.32 1.?0 1.71 4.62 2.40 7.27 -.0.7 -. 101 2.12 4.50 6,.S 5.71

0.71 .7&A 2.54 6.20 6.12 6.04

-1.00 .172 .217 .101o-01 .226 .416 -0.61 -. 226 .211 .2331.402 ,14 .208 2.13 ,496 .211 .9561-31 .175 .216

1.46 .114 .227 -. 42 -. 243 1.127

2.E0 .673 .416 .1741-02 .0.10 .406 3.66 .776 .154 3.17 2.60 .673

.243 .. 444 -. 230 .75S .110 -. 11S1t02 0.0. -. $16 -. 367 0.2 .27 3 -. 311-l01 2.22 .312 .7&6 2.12 .Silo .100

0.20 -1.02 -. 241 .0.12 - . 0.0 -. 226 2.68 -0.71 -4.30 1 -2.1 so.37 -.10& I.36 2.19 6.15 3.32 0.35 .646

1.6,0 --. 24 .1.17 .1.7 -. 213

,32. -. 111 -1.12 .1.41 .197 -. 121

.164 .6ll .156 2.22 M.02 .:22

.i729-01 .124 .167 .276 .121 .205 .162 .6441.02 .161 .215 .242 .232 .265 .6711.00 .161 .2:2 .2211 232

-. 12, ".640101 . .31A1-0s 01.63 . S1.21 -0.26

-. 132 -. 404 .716 -. 127.-00 .0.1 -01.4

.526 .339 .642 .761 0.20 a.36

2.01 2.12 1.1 .-4.79 -1.07 .S.Al 2.16 .. 2 . M -1:.41 11, -. -. 312

3.07 0.64 I.64 3 .2 .13 3 .26

.1640-01 .2819-0' .11111-41 .2361-02 .1111.01 .M121-02 .211 ,4&01.-0 .201.00 .271[-00 .2221-02 .11.02

.2l .647{1-0 .3271-01 .2541-02 .2341-02 .1140-02

4.52 .711 2.11 G.22 7.37 7.37 2.82 3.76 3.46 1.66 6.21 .t2 2.76 3.36 1.65 6.72 6.71 7.24

-3.05 -..a" .0.22 .jol11-l -. 147 IS.1

-6.11 -2.22 -. 501 .120 -. 13we-.222

6.13 2.32 .i2 2.20 .232 1.30

2.11 3.00 1." 21.00 1.25 .11So 2.72 2.57 2.6L 2.5 2.82 i.4 7

2.74 2.51 2,•6 2.64 14 1.0d

-. •0. -. ow -. 620 1.11 -. 130 -2.50

IT .0.1 ..1. 77 1 1 -0.2 1i,1 ,:9 224 1 .265 3i .7. "19 2.29 2.62 2.22 1.25 .i76 .Il6 2.26

1.21 10.0 .350 2.34 .I60 -2.22

2.37 1.32 0.05 1.26 . -. 10

2.91 1.23 2.94 -4.613 -7.71 .01.3 S4.06 .6l1 *.07 "2,61 -4.04 -4.18

6.J13 i.2 _2.2 113. 6.05 10.0

-7.70 1.63 .210 -. 430 .4.04 f i -2.76 -7001 *,347 - .41. -2.2l -4.26 2.72 .702 I.n 2.27 2.41. 6.4.

-21.9 .71.S .011.1. -as.7 .23.6 .16.2

-2.56 .42.2 -47.6 01t. .64.2 1 .64 2.0 .64.0 100. 66.2 07.6 00.0

10.1 -68.0 -22.7 -46.5 -60.5 -40.2

26.1 *ll.0 -41.1 77.31 -42.8 -63.4 "1.8 23.0 61.0 44.0 86.8 S3.1

011.2 .34.1 $4.6 16.3 .2.17 -04.7

7.11 -U6.6- 2.06 66.0 7.l7 -5,71 7.51 22.0 27.2 1&. 7 7.60 5.23

2.64 -32.6 • .01 12.5 .24.3 -30.2 28.6 -21.4 -22.0 29.3 .14 -23.3

22.2 28.6 26.1 30.5 20. 23.6

3.47 -1.8 &0.& -4.06 -47.2 -24.7

32.0 -01.2 02.2 34.7 -10.6 .25.7

6.2 :7.37 22.1 32.0 13.0 27.I

-3.41 -l.42 1.6. 4.85 .1T0 -G.tl 02.2 -.6.2 30.6 26.7 2.26 -2.52

26.2 20.1 31.7 37.2 2.4 33.70

-7.21 1.32 22.6 2.12 .4"0 -4.91 -2.21 -2.26 20 2 7.23 2.42 -2.10

4.11 3.4 122.3 10.3 1.63 3.-1

.10.4 .l4.5 l27.7 -01.1 016.2 -1@.? -. 76 .0-14:1 *6,2 .2.: * 17 11 7 :1*0

7.46 24.5 4A.2 25.0 2.a7 17.0

-. 2S11-0I .. 713C-07 -. 761-02 -. 907!-C0 -. 2271-02 -. 111-.02 .101-02 -. 3221102 .3211-02 -. 3641-02 .61-f02 -. 2C6F102 .1361-02 .. 710 .7631-02 .7311-0, .2S21-02 .:161-02
STUDSVIK ENERCITEKNIX AB STUDSVIK/NP-8&/109 Appendix C.3(4)

1986-10-28

Case C

9cauWt IO.?u.-42"1100111 0*76 yfti3?*ltu1Y 44*8.7661 t0oo4lO

F261 :.1. D03761NS14 WWI-' CAA.CU1 MO I1*V"16401 UP491MI-uIft 0*7* A? M* 01 1-t 36?66V&'.

13. US01 84 O3PFROME6~~t ~ OV,

lulft 1.104 I Mumato 4 046 W 01 644"" 4~ 3 6M0 am "W 0, 'm1 0ZI#16111C4

.11... 78 IU~t3IN&. ...

CAL.61 186. 0.0 - 1.000 - 4.000 - 7.000 - 10.00 - .0 * 10.20 - 17 00

63I4. 03 4 14.211:.02

.3U1-0'I

a63c . 6 .814

6040*0 6 .. 334

to.A

OM 0 yo -. 964

.6An2

Pm 0 cc6 .930

3.61

Wit0 - V402 .2044.41

W" - am .383

862 - 1W0 6.06

'. so

Wu6 -00 1302

I.1"

6.41

"tc - 1.66

I *1

TM - .104 .1.42

.46.

1.710.61 1.76

3 .16

41.

1.12.6 64.Ma

31.

T670 is61 .460

3.10 1kV 66l 3.011

Wit0 - JIM .6112-1.

.001-41

:318040 1

,.16S1-01 -. 6171-Of -.116 -. 01.VI- -.:11`1.' -. 101 .3I061.01 .66f1.01 .110

- 1711.01 -.134,01 .176 -. 8914-02 -. 140101 - ?14.6.01

.1161101 166W-01 .2161.01

.1It .611 .310 .U9? .146 .416 .66 .76 •?0 .466

-I .1| 1.61 .640

.1 "4.1

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'.n6 1.0? -.. 6?

1.36 tl.11 i!31

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I .6.II I. -4.21 4.14 2.411 ,4.4

3.0

3.11 .110 is 6.

-. 1 -. 13461 .110

8141.01 .4 0 .11-01 to1 I. 1 .- I4 10

.110 .4126401 .114

1.36 .36 *332

is1 1.36 .148

,11410 .411-0•1 ,IM1-0 .11l -I .4601 .l661-0l .1-.116 •.4260 -. 64.01

.III III 1041

4.| * 36-.7

3.2630 ..

6.16 3 .26 -773

2.11,4 11-41 .6601-4

.1.60 .1.49 .1.

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1.00 -. 6| I. 6.0 .63

6.13.•J .326 -. 1.4

4.63 1."I .6s

1.10 .2.1 .14.6

-*3. 0 .3642 .4.41

.8.0 -.-.11 11

,.:, .4. .46.

31.1 .43

.4.6 .11 I•. I.II

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3i 4.6 3 "

4.4 l 1.6 112

10.6 -. 4 as. 2$.1 .--. 3 "42.6

31 .29 33.6

s.3 14.1 64.1

36. 16. 47.1'l:

-1.41 .62 11

41.0 3.76 6.6?

43.4 1.1 .3.1

3,1. -6I411

IS. 36:,1 41.

.11.7 .II1 21.

-V,4R -0 ,1a -:1 1,I 4 .l " ,I 9.1 -T,

-. 164 -. 206 .I14 .364

-. I170 -. 361

-. 14 3 .134 .260o

.Ii0 .I11

.613 .I06 .11? .636

3.40 1 1.3 1.34 l.l?

.3770-41 .201

.41-1.01 .142

.. 6 .144,

-I ,31 -I,31

-.366I ,111-411 .811 .116

13.0 A 1P4

1.34 7.20

11.3 6.61

,%44 -.636141 -,377 -. 111

Mo30 .360

.300 .161 ,311 .213 .260 .360

*1.3 *1.43

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.1461101 ., 111-01 .1344-01 .464 -0,

6.32 1.71

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-.680 -6.04 .414

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-1.24 .4.71

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-.6S61 -3.1'1

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-3.A? -14.3 -4.23 -21.0 6.34 11.3

0. -2.23

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11.0 -1.3

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-4310 -. 064. 1.63 .71.4 43.6 71.3

33.3 .7.06

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93.4I

1.31

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el4,

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10.3

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STUDSVIK ENZERGITE}WIK AB STUDSVIK/NP-86/109 Appendix C.4(4)

1986-10-28

Case D

CA€CULATIOe*T0.-CPtRIlaff 0t* U8.SCtARU30 ApOkLYSIS #OR NM4JCAc.

P21ST LINI OIUI[I..el 6f4Ir•| CA4LC"3TCt "90 (AVI6A010) 93lCM[luINTAL DATA AT tN0 OFr T• tw0 .

560.0 LINI( WEAP IPPI C%3t *VIAI Tb, IPeT[MVAk,

733360 M( WI mX ! W CV MI W( 1t*VAL (MOT MEA SOuat OF p CIP 11P,14t~)

* C0S - - - - - T 1 UIPMAL - -....

CALO. axe 0.0 - :.000 * 6.000 * 7.00 - 10.00 * 15.00 * 20.00 *27.0

P 10 0 3 -. *301-02 -. 271 *.0- *.21.410 1.630 * 702 .1221-C? -*2l8(.03 *.1321-01 -.316 o.295 - 102 * S65

.3016-01 .2621-0• .164*-03 .136 .291 .10? .1:6

P 20 P 4 .21t-.01 .311300( -. 221 .. 312 -.588 -.67A .3I131-0 .21.03 ** I ".*1.*, -.326 :.32 - .*a -. 646 .1726.01 .3-J.3 01 .N101-C .360 .26O .6W4 .64

P 30 - • .370 .346 .266 -. 040O-02 -. 132E-01 -. 328 -4.34

3.62 .1 :,14 .36 .36 6 .. .-I 2.62 .3?7 .330 .113 .138 .211 .332

004* 0 4 -2.64 .2.8 .all, .813 5.37 2.84 7 1

21.6 *3.21 .2.62 2.:. .119 7.70 1.67 3?.1 .32 360 3.21 8.62 1.36 .3:

P0 0 LO -2.0• 1.13 :.:11 -. 2291-0l• .317 .422 el3.63 *31 -. 6*,07 -. 6216.03 -. 213 1.03 .312l .2i0

.s 3.91 .444 .7604-03 .6447903 .173 .377

P=* 0 CO 3.37 3.74 -2.82 -. 603 -. .11 632 -.-. 116 234 .. -2.62 !.13 -3.00 1.17 -. .812 326

4.31 2,73 I.63 .135 2.l3 3.86 .111

PC * 0 to .732 -.16•2 .4617 -. 121 .40S *..I1 -.326

.331 .11.3 13**l0 -. -. :312 .722 -. 5701901 -.326 •.41l .82 .132 .34u .:o? .124 .3Il

PM - 0 00 * 427 -.2606.03 -3.23 -2.13 .212 .. 32A .Its -3.62 2.63 -3D.03 -. 02 -. 196 .468 -. 27d 3.68 3.06 6.33 3.18 3.36 3.36 .i1s

P0O0 * 0 16 1.111 -3.92 -. O6 -. 4110 -. ll -. 160 -. 217

.631 -.62 -.612 -. 111 -.6147 -. 301 222 3.7 961 .1:0, .8 .66 .377 .272

BASIC - 3402 .3761-M0 .6771-01 .112 .203 .249 .202 .266

.120 .216-01 .66)1-01 .174 .324 .301 285 .A1" .1331-03 .7363.03 .375 .341 .310 .290

l20 * 103 -.302 -. )•13 *.2 *.4 -3.87 .3.59 -1.47 -. 16 -. 7 -AN".22, .4036-0•3 -.327 .46 31.66 .78l .378 .3J71 .343 .593 3.66 3.67

W30 * SS0W 6.93 4.92

8.62

.367*d .214?

- 5430 -2.32

.7,86

1.08

:60 . P4M -11.0

32.2

TVID - T is .960 112~r0 * 1 36 .2.3

TV$0 . T 35 .963

rplo TC 11 3.67 3.78

6.07

1150 . t 34 4.514 "-35.0

3.13

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2.&A

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20.3

3T60 - Te1l 6.52

WT70 - Tell .100

2.36

MI.l - 3473 -3.?7

20.?

3.29

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.336

.322

-1 .904.13

IVU 325

.3.8

3.8

-6.28

1.164

1 .37

.4.30

-24.3

--vs'.$

,.4. 86

.6*3

-4.8

132.0

-29.1 *:90

2 7.6

29.1

-95.8

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87.6

.10.1

17.6

-2.66

30.8

32.8

-4.36

2.01 *."s' -*.33 2.65 2.61 3.03 3.31 -.13.53 o.68

.56.03 * .1831-01 .401-47

.6436.01 .1411-01 .6800-02

-3.35 -1.27 6.00 .. 37

".30•f-0a -.*218-03 .281-061 .3813-01

l.35

2.61 3.23

.179

-. 814

70101.01

3.30

2.1

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2.60

1&:4

3.73

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3.42 5.13 7.53 7.60

3.2 613 .52 7.61 2.20 4.1, 6.1U 7.12

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.639 3.06 .IS0 1.33

-. 380 -6.30 -4.12 -35.2

3.36 -3.6 -4.23 .13.3 3.68 3.76 6.6i 12.8

-2.68 -4.51 -30.3 .20.1

NO.6 3 .431, -. 4 2.85 3.98I 9.67 36.3

.3.$4 ..4.0 -0.71 -13.7 -.~26 -23 .717 1-6.I .116 2.68 7.37 '6.3

-6.3 -33.5 .30.2 -2.3 -. 264 37.43 -36.0 -22.6 3.•6 61.3 16.3 23.0

-12.6 -36.3 -241. -12.6 -4.44 -.1.3 .20. 3 -21. 6.33 14.3 20.6 3,.3

.47.7 .81.7 -22.0 -30.1 -47.8 .309. -42.3 .2 58.3 305. 64k.2 33.8

13.1 -89.8 -41.0 .63.t 7.66 -. 0.4 -71.0 -41.3 10.3 "6.: 72.7 63.4

34.0 -70.6 134.9 -4.12 .37.2 -27.2 .26.1 .33.,

64.8 16.4 2I.3 133.

-116. 0118.3 -. 3 :2.3

-306. 3051. 30 333. -41. 52.3.: -23.5: 35.6

42.2 -2.80 -0.62 6.46 27.6 3.13 4.S.0 .4.00 33.7 30.1 6.74 5.03

8.63 39 0.7 36 7.72 -. 68S -4.,t0 -3.33

9,47 3.6 6.6.2 6.73

-4.82 -i.37 -4.92 -4.41 -4.21 -735 .1 $.88 ?.7.6

9.3s 7.45 $.92 7.82

-. 7951-02 -. 3071-02 -. 2171.02 -. 331-0 .2231-02 -. 431f-02 .2571-02 -.3123-12 .?73 1-02 .0632-02 .1636-02 .2431-02310 * 3303 . -22f.03 -.251t.01 -.7139-02 .30O0-01 .1691-02 -. 3216-02 .12606-03 .1711-03 .3311-031
STUDSVIX ENERGITEKNIK AB STUDSVIK/NP-86/109

1986-10-28

Appendix D.1(1)

APPENDIX D

Description of the accompanyiAq data package

STUOSVIK

THIS TAPE CONTAINS DATA FROM THE ICAP PREDICTION CALCULATION

WITH THE RELAP5/MOO2/36.04 FOR THE FIX-Il EXPERIMENT NO. 5061.

CONTENTS. FILE I .

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

THIS DESCRIPTIVE TEXT

INPUT CASE A. STEADY STATE - "- A. TRANSIENT

- B. STEADY STATE

DATA. EXPERIMENT - CASE A - CASE 8 . CASE C

" CASE D

CYBER 170-810

60

9

1600 BPI

80

64

EBCDIC

NO

I. COMPUTER NAME

WORD SIZE

1I. TAPE FORMAT

NUMBER OF TRACKS

PACKING DENSITY

RECORD SIZE

BLOCKING FACTOR

CODED

.CONTROL WORDS

III. DATA FORMAT. FOR EACH OF THE FILES 5 THROUGH 8

TITLE RECORD(S), (FORMAT 15.A75)

FIELD 1. THE NUMBER OF DATA CHANNELS ON THE FILE

FIELD 2. PROBLEM IDENTIFICATION

UP TO FIVE ADDITIONAL IDENTIFICATION RECORDS

MAY BE ADDED BY 'C' IN COLLUMN 1 OF FIELD I

DATA SET RECORD 1. (FORMAT 215.A60)

FIELD 1. NUMBER OF DATA POINTS

FIELD 2. THE ENGINEERING UNIT CODE CEUC) FOR THE

VARIABLE

FIELD 3. IDENTIFYING TEXT OF THE DATA

REIAINING DATA SET RECORDS FORMAT 5CE16.9)

EACH DATA CHANNEL SUBMITTED IS GIVEN THROUGH TWO DATA

SETS. THE FIRST OF WHICH IS THE TIME DATA SET.

THE TWO SETS HAVE THE SAME NUMBER OF DATA POINTS.

THE TIME DATA SET IS IDENTIFIED BY EUCw77 (FIELD 2)

AND THE IDENTIFYING TEXT 'TIME' (FIELD 3).
IL
MAC FORM 335. U S. NUCLI• A REGULATOR L V OAMM411O01 I S aVO T NmUMBER A ,,# Or 1`10C E VV IV. ,-.,#-0

' 110NUREG/IA-0016

3201.102 BIBLIOGRAPHIC DATA SHEET STUDSVI K/NP-86/109 $11 00NSTAUCTlONS ON ?VI VISPt St 

2 TITLIA* AN0suTITkI J IAJAVl OLA lK

Assessment of R ELAP5/MOD2, Cycle 36.04 Against

FIX-II Guillotine Break Experiment No. 5061 4 DATE ME-R' COMPLA'ED

MNT. I VIAM

5 AuJTmomISi

John Eriksson , OT R,,ORT SSUEO , 

JuEI AR

July 1989

7 PERFORMING OAQANIZATION NA'ME ANO MA.I.ING ADDRESS II•.•0 "o I PAOJICT/TASI/WORK UP41T NUM6Ei

Swedish Nuclear Power Inspectorate

P.O. Box 27106 ,,,NORGRANT NUMER

S-102 52 Stockholm, Sweden

10 SPONSORMNG ORGANIZATION NAME AND MAILING ADORESS IMCwMP Z. COW, It. TYpe OF REPORT

Office of Nuclear Regulatory Research Technical Report

U.S. Nuclear Regulatory Commission 0. PIIO COV1o1O ,--*--

Washington, DC 20555

12 SUPPLEMINTARY NOTES

13 ABLSTRACT rW W10. 0 -Pef

The FIX-II guillotine break experiment No. 5061

RELAP5/MOD2 code. The code version used, Cycle

of the code.

has been analyzed using the

36.04, is a frozen version

Four different calculations were carried out to study the sensitivity of

initial coolant mass, junction operations and break discharge line

nodalization. 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 break mass flows were generally underpredicted at the same time as the

depressurization rate was overpredicted.

14 DOCUMENT ANALYSIS. a tWOROVOIESCSPTORS IS AVAILABIL.ITY

RELAP5/MOD2, ICAP Program, FIX-II, Guillotine Break STATEMENT

Unlimited

I. SICURITYVCLAIPICAION

SOIN,,IF,,SIOPIN INDO, TERMS Un.classified

Uncl assified

I I NUMI116I Of PAGES

Is PRICE
Ii

11

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

SPECIAL FOURTH-CLASS RATE POSTAGE & FEES PAID USNRC

PERMIT No. G-67