NUREG/IA-0166

International

Agreement Report

RELAP5/MOD3.2 Assessment

Using GERDA Small Break Test, 1605AA

Prepared by

W Tietsch

ABB Reaktor GmbH

Dudenstrassee 44

D-68176 Mannheim, Germany

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

July 1999

Prepared as part of

The Agreement on Research Participation and Technical Exchange

under the International Code Application and Maintenance Program (CAMP)

Published by

U.S. Nuclear Regulatory Commission
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NUREG/IA-0166

International

Agreement Report

RELAP5/MOD3.2 Assessment

Using GERDA Small Break Test,

1605AA

Prepared by

W Tictsch

ABB Reaktor GmbH

Dudenstrassee 44

D-68176 Mannheim, Germany

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

July 1999

Prepared as part of

The Agreement on Research Participation and Technical Exchange

under the International Code Application and Maintenance Program (CAMP)

Published by

U.S. Nuclear Regulatory Commission

A BB ABB Reaktor GmbH

F & E - STUDY Blatt I von 31

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Kunde:

Customer:

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GBRA 045 127

Titel:Iritle: RELAP5/MOD3.2 Assessment Using

GERDA Small Break Test, 1605AA

Anlaqen-Kennzeichen:

System-Code:

ABB Reaktor GmbH, Mannheim, December 6th, 1998

written: AM - Dr. W. Tietsch

geprOft

approved:

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AM - G. Breiling cf.....

A . .K . .... . .. . AM -K. Benitz

FOr dieses Dokument und den darin stellten Gegenstand behaften wir uns ade Rechte vor. Vervielraltigung, Bekanntgbe an Dritte oder Verweftg seines Inhalts sind ohne unsere ausdrucldiche Zustimmung veorben.

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We reserve all rights in this document and in the Iformation contained therein. Reproduction, use or disdosure to third parties wbthout express authority

is strictly forbidden. 0 ABB Reaktor GmbH 1999

NRC.003.DOC . AM-OrfTas
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Anderungsblatt

Revision sheet

NRCOOIOC- AA&MMSV~
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ABB Reaktor GmbH

lnhaltsverzeichnis

Table of Contents

Titelblatt

Anderungsblatt

Inhaltsverzeichnis

Zusammenfassung

AbkOrzungsverzeichnis

Cover sheet

Revision sheet

Table of contents

Abstract

Abbreviations

1

2

3

4

5

I Introduction 6

2

3

3.1

3.2

3.3

3.4

3.5

3.6

3.7

3.8

3.9

4

4.1

4.2

4.3

4.3.1

4.3.2

4.4

4.5

Description of the GERDA Test Facility

Description of the Experiment 1605AA

Initiation of the test

Subcooled Draining, 2 to 6 Minutes

Saturated Spillover Circulation, 6 to 8 Minutes

Intermittent Circulation, 8 to 22 Minutes

Stalled Flow, 22 to 35 Minutes

Boiler-Condenser Mode, 35 to 52 Minutes

Hot Leg Refill, 55 to 110 Minutes

System Refill, 110 Minutes and Beyond

Synopsis

RELAP5 MOD 3.2 Analysis of Test 1605AA

Code Description

Modeling Description

Conditioning Calculations

Steam Generator Steady-State Performance

GERDA 1-Loop Model Steady-State

Calculational Procedures

Results of the Post Test Calculations and Comparison to the Test

Conclusions

References

List of Figures and Tables

7

9

10

10

11

12

13

14

15

16

17

18

18

18

20

20

21

22

23

27

28

5

6

7 29

Appendix A: Figures and Tables A1-A49

Appendix B: Input Usting of GERDA Model B0-B62

NR~C-CO3 C - A&&r~h'ts
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1515lbiCA U4.S d(U blam I rage A B iABB Reaktor GmbH

Abstract

The Small Break Loss of Coolant Accident (SBLOCA) Test Facility GERDA (Geradrohr Dampferzeuger

Anlage) was designed to evaluate the post SBLOCA thermal-hydraulic events expected to occur in the German

M0lheim-Krlich plant. The scaled in volume 1:1 in height Test Facility was built and tested by B&W at the

Alliance Research Centre (ARC) under contract of BBR (Brown Boveri Reaktor GmbH) now ABB Reaktor

GmbH (Ref. /11,/2/). The objective of the whole test program was to obtain detailed experimental data for the

evaluation of single and composite SBLOCA phenomena and for the verification and the refinement of the

analytical tools and models used to predict plant performance during SBLOCA transients.

This report presents the results of RELAP5IMOD3.2 assessment on the integral (composite) GERDA Test

1605AA which features a complete sequence of a 10 cm2 Reactor Vessel Leak transient conducted on April

12th, 1983. The purpose of the assessment analysis was to determine whether the tested RELAP version can

predict the major phenomena of this complex transient and to provide some useful information both to code

developers and analysts for the application on SBLOCA transients in 'Once-Through-Steam-Generator Plants.

The results of the post test calculations were compared to the test data. This comparison has shown that in

general most of the important phenomena are predicted quite well. However differences in details such as

timing of key sequences and some disagreements, such as over and under predictions of certain key parameters were observed. In general it was concluded from the comparison that the predictability of such complex

transients, especially the BCM (boiler-condenser) phase, is fairly good. However there were several deficiencies discovered mainly in predicting OTSG behaviour, leak flow and the refill phase during SBLOCA in an

OTSG plant These finding should be used as a target for further fine tuning and enhancements of the code.

Additionally this report presents some base calculations identified as conditioning calculations of OTSG steady

state and transient behaviour which is one of the essentials for the prediction of phenomena observed in the

SBLOCA scenarios.

Finally a complete input listing of the RELAP5MOD3.2 GERDA model is included in appendix B.

The analysis presented here and the report is an inkind contribution to the CAMP contract.

1,

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Abbreviations

ABBR/BBR ABB Reaktor GmbH

AFW Auxiliary Feed Water

ARC Alliance Research Centre, Ohio

B&W Babcock & Wilcox

BCM Boiling Condensing Mode (Phase of Transient, Heat Transfer)

CAMP Code Assessment and Maintenance Program

CL Cold Leg

DAS Data Acquisition System

DC Down Coiner

FP Full Power

FW Feed Water

GERDA Geradrohr Dampferzeuger Anlage

Straight-Tube Steam Generator Test Facility

HL/HLUB Hot Leg / HL winverted" Loop (U-) Bend (Candy Cane)

HPI High Pressure Injection

HPV High Point Vent (Hot Leg)

IEOTSG Integral Economiser OTSG

KMK / MK M01heim-Knrlich Nuclear Power Plant

KWU Kraftwerk Union

LOCA Loss of Coolant Accident

NPP Nuclear Power Plant

NSSS Nuclear Steam Supply System

OTSG Once Through Steam Generator

PKL Primftreislauf, Primary Coolant Loop Test Facility

PORV Power operated Relief Valve

PRZ Pressurizer

RPV Reactor Pressure Vessel

PWR Pressurized Water Reactor

RCS Reactor Coolant System

RSK Reaktorsicherheits Kommission (German Reactor Safety Board)

SBLOCA Small Break LOCA

SG Steam Generator

VV Vent Valve

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I Introduction

Since many years Small Break LOCA scenarios are in the centre of interest both for licensing bodies to

understand the complex phenomena and learn about the accompanying risks and for code developers to

increase the capabilities of licensing codes and to implement specific physical models and enhancements.

The Probabilistic Risk Assessment activities in the US and Germany and especially the TMI-2 event in April

1979 raised quite a number of additional reactor safety questions in the early eighties mainly in the area of

post-SBLOCA system performance. Particularly plants with the Hot-Leg-U-Bend Once-Through-SteamGenerator (HLUB-OTSG) configuration underwent thorough examinations. While in the US B&W had already

built some nuclear power plants with OTSG in the seventies, in Germany only one plant of this type, MO•heimK~riich NPP was under construction since 1973 by a consortium of BBR and B&W.

Electrified by the TMI-2 problems and the regulations of the German Reactor Safety Board (RSK-LL) BBR

consented to conduct experiments to remove the concerns about SBLOCA transient behaviour. As B&W

already had some test rigs in ARC at that time, featuring mainly coupled Pressurizer and OTSG models used

so far for code verification, BBR and B&W contractually agreed in 1981 to build an independent test loop for

SBLOCA transients named GERDA, an acronym of Geradrohr Dampferzeuger Anlage which is German for

OTSG plant (Ref. 11,/12/). GERDA pretest prediction analyses were performed through spring 1982, characterisation tests mid of the year. SBLOCA testing was begun only a year and a half after contract award, and

it extended from September 1982 through April 1983. In total 112 tests have been performed in two campaigns

including characterisation tests used to determine loop characteristics and to exercise specific loop features

such as instrumentation, vent valve actuation, cool down control and others. In the second phase SBLOCA

scenarios were addressed in detail. This testing followed a progression from separate-effects to composite,

integral-system testing. In this phase testing was performed in five categories: Steam Generator Heat Transfer,

Natural Circulation, Boiler-Condenser Mode, Refill and Composite Tests (Ref. /3).

For the RELAP5IMOD3.2 assessment presented in this report a composite integral test (Test 1605AA) was

chosen which is a complete SBLOCA transient and which was performed on April 12t 1983. This test, selected

as the nominal composite test, represents a 10 cm2 Reactor Vessel break with 2 out of 4 HPI trains available.

The test scenario covers the transient from leak initialisation, loop saturation, Boiling Condensing Mode (BCM)

and primary refill. In this report a post-test analysis of test 1605AA applying RELAP5/MOD3.2 is presented.

An overview and description of the GERDA Test Facility as well as of the test and the test conditions are

provided. The RELAP input model of GERDA test 1605AA is described. The results of the calculations and

the correspondence to the test phenomena are discussed and finally the conclusions and recommendations

from this assessment are presented. An input listing (limited distribution) is attached in the appendix. The

purpose of the presented analysis is to add experience to the CAMP community, applying RELAP to OTSG

plant transients, and to serve as an inkind contribution to the Code Assessment and Maintenance Program.

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2 Description of the GERDA Test Facility

The Small Break Loss of Coolant Accident Test Facility GERDA was designed to evaluate post SBLOCA

thermal-hydraulic events for the 1300 MWe German M01heim-Kdrlich plant, which is based on a license of

B&W's 205 NSSS design. A principal drawing of the primary loop of the 205 design is shown in Fig 2.1. The

main difference to the typical B&W 177 plants like Rancho Seco or TMI (Fig. 2.2), apart from power level and

core design, is the raised loop configuration and the Integral Economizer OTSG (IEOTSG). The typical OTSG

has feed water preheating in the feed water downcomer by the admission of rated life steam flow from the tube

bundle to the top of the downcomer through aspirator orifices. In the IEOTSG design the feed water enters the

tube bundle section subcooled and is heated to saturation in the lower part of the SG. In this design the steam

superheating is enhanced to 38 K at FP. The main SG characteristics of both designs, 177 and 205, is seen

in Fig. 2.3. In view of modeling SG with RELAP the IEOTSG is simpler to model because of the absence of

downcomer feed water preheating but more challenging with respect to thermal dynamics because of the

complete set of heat transfer mechanisms and flow phenomena along the tubes (subcooled to superheated).

GERDA was built and tested by the B&W Utility Power Generator Division at the B&W Alliance Research

Center, Ohio, under contract of BBR (Brown Boved Reaktor GmbH) now ABB Reaktor GmbH. The Test Facility

was intended to be primarily used to evaluate separate effects and integral system tests at scaled power

levels between I to 5% . The objective of the whole test program was to obtain experimental data for the

evaluation of all significant SBLOCA phenomena and for the verification and the refinement of the analytical

models used to predict plant performance during SBLOCA transients. SBLOCA fluid behavior is typically

buoyancy-driven in major transient phases, thus full elevation modeling was the main priority for scaling. The

Test Facility therefore retains an MK elevations. Full elevations, of course, do not guarantee for all plant-typical

post-SBLOCA phenomena. Therefore all governing important SBLOCA phenomena (e.g. HL 2-phase flow

behavior) have to be preserved as a second scaling criteria. All components are scaled with respect to volume

by the ratio of the steam generator tubes (32026/19=1685,6). Finally, loop irrecoverable losses are conserved

by use of orifices to match original MK losses.

With this scaling philosophy piping size has been selected to preserve the (vapor) Froude number, and thus

the ratio of inertial to buoyant fluid forces. This preserves flow regimes according to well known flow maps and

flooding criteria. System pressure and temperatures are not limited in the Test Facility as in other facilities. The

test configuration consists of a 1-by-1 model loop (the prototype plant KMK has 2 x 4 loops) which is approximately 95 feet (29 m) high and about 6 feet wide, see Fig. 2.4, including an electrically heated Core Simulator,

1 Hot Leg, a 19 tube model OTSG with full length tubes, 1 Cold Leg, and a Pressurizer. The prevalent power

and volume scaling factor is 1685.6 and 1400 respectively, the model core power is limited to 178 KW

corresponding to - 8% of nominal full power. The ratio of power and volume is 1.2 (1.1 for SEMISCALE 2A,

1.0 for LOBI). The scaling used for GERDA allows for similar time dependencies of the major events in the

tests and the prototype plant.

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Primary components include a rector vessel vent valve (VV), Pressurizer PORV or Safety Valves, High Point

Vent (HPV), High-Pressure Injection (HPI) into the Cold Leg, controlled primary leaks, Auxiliary Feedwater

(AFW), and a simulation of the MK 48-bar Steam Relief Valves and Cooldown Valves. No primary reactor

coolant pump is included in the basic loop. A multi-purpose pump in a CL bypass line can be used to provide

forced primary flow.

Some details of the test arrangement are shown in the following figures. In Fig. 2.5 the 19-Tube OTSG model

is presented. It can be seen that additionally to the MK typical IEOTSG design an alternate steam/feedwater

mixer is available for OTSG type 177 evaluations. One main phenomenon during BCM is the spillover of

steam/water mixture from the HL via the HLUB into the upper plenum of the SG. The model HLUB (Fig. 2.6)

is designed to preserve the spillover elevation and to guarantee that voids in the HLUB separate and accumulate at least as likely in the model as in the real plant. In Fig. 2.7 and 2.8 some other details of scaling and

preserving of basic geometric dimensions are shown.

In addition to the customary pressure, temperature, level, and pressure-drop measurements, GERDA included

HL optical ports, primary and secondary conductivity probes for level, and a CL acoustical (supersonic) flow

meter to measure low natural-circulation flow rates. More than 300 parameters could be monitored simultaneously for each test by a heavy duty data acquisition system. Type and locations of instrumentation are given

as an overview in Fig. 2.9 and in detail in Figs 2.10 and 2.11 . In appendix A (Table 2.1) a list of all instrumentation used for this test 1605AA is provided in order to be able to identify the parameters on the original data

plots.

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3 Description of Experiment 1605AA

GERDA test 1605AA was conducted on April 12t 1983 in the second phase of testing which addressed

SBLOCA phenomena. The test series 16 belongs to category 5, composite effects test, i.e. complete SBLOCA

transients. This test series investigated system interactions following SBLOCA. Leak size and location as well

as HPI capacity were varied. The nominal sequence of events included draining, saturated spillover circulation,

intermittent spillover, punctuated primary depressurisation, stalled primary flow, BCM, HPI flow greater than

discharge flow, HLUB spillover by refill, and finally reactor vessel refill. The main interest focussed on the heat

transfer from the core to the heat sink provided by the SG, especially in the BCM phase of the transient, and

on system refill and integral system behaviour during cool down.

Composite test 1605AA investigates a scaled 10 cm2 Reactor Vessel (RV) leak with two (2) scaled High

Pressure Injections (HPI) Pumps. The transient was tested through refill and was intended as the nominal test

for the other tests in this series.

At test initialization the primary system is subcooled at forced flow conditions. The primary pressure is 2170

psia, the Core outlet and the Hot Leg temperatures are at 605 F, Cold Leg temperatures are at 570 F.

Saturation temperature and Pressurizer fluid temperatures are at 648 F, the PRZ level is 11 feet, the Surgeline

metal temperature is approximately 625 F (heated from a scheduled pretest system drain evolution).

The core is powered at 5.2% of scaled full power (1% = 22.3 KW), Primary flow is 9% of scaled full flow (1%

= 0,263 Ibm/s), the Reactor Vessel Vent Valve (RV VV) is shut dose. RVVV - bracketing temperatures are

570 F and 540 F, the RV Upper Plenum fluid temperature is 563 F. Loop flow resistance is nominal.

The Steam Generator (SG) Secondary is being maintained at 1150 psia (Tsat = 562 F) and 11 ft level. The

steam flow orifice simulating two (2) 48-bar steam dump valves is installed. AFW (Auxiliary Feedwater) is being

injected at 120 F using the lower-elevation (MK situation) and minimum-wetting nozzles. SG heat removal is

4,5% of full power, steam and feed flowrates are 3,3% of full flow (1% = 0,0263 Ibm/sec). At 1024 on April 12,

1983 the Data Acquisition System (DAS) is activated; this defines zero time for the data plots and for the

discussion following. The entire Test 1605AA sequence is summarized in Section 3.9, a detailed sequence

of events can be found in table 3.1 in appendix A.

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3.1 Initiation

The test is initiated in two steps, to approximate plant-typical conditions at and after loop saturation. Power

level at DAS activation is 5.25 % of full power. The first group of initiating actions are taken between 2 and 3

minutes after DAS activation:

- Adjust core power to 4.4% of full power

- Trip and isolate the Primary forced circulation pump

- Open the 10 cm2 RV leak

- De-energize the PRZ main heaters, and increase the PRZ guard heater bias

- Realign the W controller to open/close the VV at +/- 0.005 psi Upper Plenum to Downcomer

pressure difference.

The second group of initiating actions is taken at the approximate time of loop (HL U-Bend) fluid saturation.

These actions, taken at approximately six (6) minutes, are:

- Realign the SG Secondary set points to obtain 48 bar (700 psia) steam pressure and "Mr' level

using two (2) simulated AFW pumps

- Actuate the core power ramp controller to simulate power decay; and

- Actuate two (2) simulated HPI pumps directed to the Cold Leg (pump-) Discharge (CLD) piping.

The MK SG level control scheme feeds to 26.7', then steams down to 25' without feed, in a repetitive bandcontrol fashion. Manual feedrate adjustments are made to simulate prototypical AFW head-flow characteristics.

The aforementioned initiating actions precipitate changes in virtually every loop parameter, as discussed in

the following section.

3.2 Subcooled Draining, 2 to 6 Minutes

The Primary forced circulation pump trip at 2 minutes has an immediate effect and parallels the forced to

natural circulation transient examined in previous tests. Primary flowrate decreases to - 2% by 3 minutes (Plot

9, plot numbering corresponds to original data plots). With the core still powered (but decreased to 4.3% at

2 minutes, Plot 19), the core outlet fluid is heated increasingly with decreasing flow, attaining 620 F at 2 %

minutes (Plot 111). As flow decreases, the SG heat removal rate decreases also to - 1.5% of full power by

2 % minutes. Secondary steam and flowrates are attenuated by minutes (Plot 12), the slight lag of feed

attenuation cools the SG Secondary pool at the feed inlet by 10 F at 3 minutes (Plot 191); following feed

reduction the SG Secondary pool approaches uniform temperatures by 5 minutes (Plot 191). The primary flow

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decrease also produces some cooler SG Primary outlet temperatures at 2 Y2 minutes (Plots 132 and 26). The

net fluid density effect of these flow-induced Primary temperature changes is a slight system fluid expansion,

because the heated fluid volume exceeds the cooled one. Primary pressure peaks slightly at 2 % minutes (Plot

1), and PRZ Surgeline metal cools to 621 F by 3 minutes with the accompanying insurge flow (Plot 124).

Upon actuation of the W on automatic (-0 dp) control at 3 minutes (Plot 16), the driving pressure difference

is 0.15 psi and is decreasing (Plot 172) in response to the increasing natural circulation flowrate. The W

opens. The Downcomer flowrate immediately exceeds the Cold Leg flowrate (Plot 9) and the VV bracketing

fluid temperatures immediately equalize and increase toward core outlet temperature, attaining 610 F at 3

minutes (Plot 171). The Downcomer fluid temperatures increase as the W admits hotter fluid (Plot 151).

The Reactor Vessel leak is actuated at 2 % minutes (Plot 16). The RV leak flow attains 0.12 Ibm/sec by 3

minutes (Plot 17). The PRZ Surgeline metal temperature increases with the outsurge due to draining, reaching

640 F at 3 % minutes (Plot 124). The Pressurizer inventory is depleted by 3 % minutes (Plot 4); the pressure

falls rapidly (Plot 1) reaching 1700 psia by 51⁄2 minutes. The Hot Leg Fluid temperatures increase dramatically

from 3 to 5 % minutes, due to both the Primary flow reduction and the introduction of saturated PRZ fluid (Plot

121); At 4 % minutes the temperature probe HLTC02 at 9', just above the Surgeline connection to the HL,

attains 622 F (Plot 121). The HL Conductivity Probes indicate HL voiding after 4 minutes (Plot 123). The HL

metal temperatures respond rapidly (Plot 124); these temperatures at 34.5' have increased from 605 F to 618

F by 5 A minutes, and to 615 F by 6 minutes at 66'. At 5 minutes as the PRZ voids, the PRZ fluids, at saturation temperature, and the Surgeline metal temperature fall abruptly to the current HL fluid temperature,

-620 F (Plots 124 and 161).

The primary fluid temperature changes accompanying pump trip at 2 minutes have generated an increasing

natural circulation driving force; the natural circulation flowrate peaks at 6% of full flow at 5 minutes (Plot 9).

In response to this renewed flow, the SG heat removal has returned to -5% (Plot 19). The SG Primary outlet

and Cold Leg fluid temperatures returned to -570 F between 5 and 6 minutes (Plots 26 and 132). At approximately 6 minutes, the Hot Leg and Primary saturation temperatures merge (Plots 102 and 121) and the HLUB

saturates.

3.3 Saturated Spillover Circulation, 6 to 8 Minutes

At approximately 6 minutes, the HLUB (Hot Leg U-Bend) fluid is observed to saturate and the second group

of initlating actions is taken: The SG Secondary control points are reset to 48 bar (700 psia) using 2 simulated

dump valves and MK level controls 25' to 26.7' band control manually simulating the head-flow characteristics

of 2 AFW pumps); core Power is ramped to simulate decay; and the two scaled HPI pumps directed to the

Cold Leg Discharge piping are actuated.

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The Steam Generator Secondary immediately responds to the control point changes. The feed and steam

flowrates increase to 4 W/% and 3 Y% of full flow at 6 minutes (steam flow is choked) (Plot 12). The SG heat

transfer rate increases to 5% of full power (Plot 19). Secondary steam pressure begins to decrease from 1150

psia, reaching the 700 psia control point by 9 minutes (Plot 1). The combination of Secondary steaming and

pressure-retarded feeding suppresses the SG Secondary level change for these first minutes (Plot 4). But the

increased feeding does lower the SG Secondary pool temperatures (Plot 191); the lower-elevation pool

temperatures decrease from 560 F at 6 minutes to - 480 F at 8 minutes. The SG Primary Outlet and CL

temperatures respond simailay, decreasing from 570 F at 6 minutes to 520 F at 8 minutes. The downstream

Cold Leg temperatures (Temperature gauge CLTC04 and 05, Plot 151) begin to indicate HPI cooling, dropping

to 505 F by 9 minutes. The HPI, actuated at 6 minutes, attains only 0,03 Ibm/sec at this Primary pressure

(Plot 17).

During these first two minutes of loop saturation, the Reactor Vessel stays approximately full, the HL upstream

collapsed level is at the spillover elevation, but the HLUB downstream collapsed level begins to recede,

reaching 63' at 8 minutes (Plot 4). With this saturated spillover circulation mechanism available, and with the

system responding to the buoyancy effects caused by the temperature distribution, the primary flow attains

a second natural circulation maximum value of -5% of full flow at 8 minutes (Plot 9). But the primary liquid

inventory is still decreasing rapidly due to the excess of leak over HPI flowrate (Plot 17), thus the HLUB

upstream collapsed level begins to fall at 8 minutes (Plot 4).

3.4 Intermittent Circulation (8 to 22 Minutes)

At 8 minutes the HL upstream level begins to decrease, reaching 64' at 9 minutes (Plot 4). Primary Circulation

is thus interrupted (Plot 9), the Primary repressurizes to 1750 psia at 9 minutes (Plot 1), and Secondary

pressure reaches its 700 psia control value (Plot 1). Pressurizer level increases to -10' upon this repressurization (Plot 4). Steam Generator heat transfer decreases with de-coupling (Plot 19). The upper HL Conductivity

Probes reflect dryout (Plot 112).

The Reactor Vessel Upper Plenum saturates at -11 minutes (Plot 111), and the downcomer and RV inlet fluid

approach saturation (Plots 111 and 151). The Reactor Vessel level begins to drop with upper head voiding

(Plot 4), reaching 0' at 11 minutes. This voiding transfers fluid up the Hot Leg, raising the HLUB upstream

collapsed level to the spillover at 10 % minutes (Plot 4). The primary flow restarts (Plot 9), and the primary fluid

temperatures respond accordingly (Plots 121,131,132 and 151). The SG steam flow increases (Plot 12), as

does the SG heat transfer (Plot 19). The secondary steam dump valve simulation chokes and the secondary

pressure momentarily increases (Plot 1). Primary system cooling, fluid contraction, and condensation are

sufficient to depressurize the primary system back to 1700 psia (Plot 1). But the contraction plus the continuing

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loss of Primary fluid inventory again deplete the HLUB upstream level (Plot 4), interrupting primary circulation

a second time.

Two subsequent HLUB spillover occur, at 16 and 22 minutes. They resemble the initial spillover, except that

their corresponding HL upstream collapsed levels are progressively lower (Plot 4), at 65' and 63'. The spill over

at 16 minutes occurs as the RV collapsed level drops from the region of the W to that of the HL nozzle, the

later spillover occurs as the RV, Downcomer, and Cold Leg void to -6'. The ensuing condensation of the CL

and DC voids drops the HL upstream level to 40' (Plot 4) and intermittent spillover ceases.

The primary pressure is reduced at each spillover. It decreases from 1850 to 1700 psia at 22 minutes (Plot 1).

The Steam Generator Secondary refills to the control zone by 20 minutes (Plot 4). The Pressurizer routinely

refills with Primary pressurization and vice versa (Plot 4). The primary flowrate and the Steam Generator heat

transfer rate peaks are observed with each spillover (Plot 9 and 19). Cold Leg fluid temperatures tend increasingly toward saturation with successive spillovers (Plot 26). Reactor Vessel Conductivity Probes record dryer

conditions between circulation pulses, especially the upper CP's bracketing the W (Plot 112). The Hot Leg

and Steam Generator Outlet fluid temperatures reflect flow pulses by converging (Plots 121 and 132). At 22

minutes, the primary flow has again subsided (Plot 9) and the SG Secondary heat transfer is diminishing

(Plot 19).

3.5 Stalled Flow, 22 to 35 Minutes

From 22 to 35 minutes, HL levels are generally subsiding (Plot 4), Primary and Secondary flows are miniscule

(Plots 9 and 12), thus the core heat source is largely decoupled from the Steam Generator. Leak discharge

energy approximates Core heat input (Plot 19), thus the Primary repressurizes only mildly, from 1700 to 1800

psia (Plot 1). HPI flowrate is reduced to 0,015 Ibm/sec by this repressurization (Plot 17). Thus leak flow greatly

exceeds HPI flow (Plot 17) and Cold Leg fluid temperatures either stratify (Plot 141) or follow the Downcomer

and Core Inlet temperatures toward saturation (Plots 26 and 151).

Hot Leg and upper RV fluid temperatures remain saturated (Plots 111 and 121). HL and upper RV conductivity

probes indicate decreasing moisture content (Plots 112 and 123). By 35 minutes the SG Primary Level

approaches the Secondary level (Plot 4), the Primary system liquid inventory reaches a minimum of 45 % of

full (Plot 105). The insurge accompanying Primary repressurization has raised PRZ level to 15' (Plot 4) and

has increased Surgeline metal temperature to within 10 F of saturation (Plot 124). At 32 minutes the High Point

Vent (HPV) is opened (Plot 16) and the SG Secondary is depressurized to obtain the prototypical 50 F/hour

cooldown (Plot 1). Neither of these events has a major impact on the current transient behavior.

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3.6 Boiler-Condenser Mode, 35 to 52 Minutes

At 35 minutes the SG Primary and Secondary levels are approximately equal (Plot 4) and Primary steam is

condensed within the SG. The SG steam and feed flowrates increase to -4% of full flow (Plot 12), and the SG

heat removal attains 5% of full power (Plot 19).

The primary pressure is rapidly reduced by the condensation of Primary vapor. The Primary depressurization

rate reaches 200 psi/min, the primary pressure decreases from 1600 psia to 630 psia (Plot 1), and the primary

saturation temperature is reduced to 495 F (Plot 102). The influx of primary condensate (Plot 9) introduces

colder fluid into the Downcomer (Plot 151). The Downcomer refills at 37 minutes, the Core collapsed liquid

level increases from -5' to -3', and the Pressurizer drains with depressurization and with Primary inventory

contraction (Plot 4). As the primary pressure decreases, the HPI fiowrate increases exceeding the leak mass

flowrate by 40 minutes and attaining 0,15 ibm/sec (Plot 17). The net Primary System liquid volume rate of

change abruptly increases from - 0,2 to + 0,2 ftW/min. The increased HPI flowrate sporadically cools the CL

upstream thermocouple (CLTC04, Plot 151).

Although the Primary system liquid inventory is increasing , the redistribution of this liquid towards lower

elevations, with condensation of primary vapor decreases the moisture content of the higher Primary elevations. The Hot Leg fluid temperatures decrease with the primary saturation temperature. Then, successively

with the decreasing liquid level in the HL, the HL fluid content remains superheated by as much as 70 F (Plot

121). The HLUB metal behaves similarly (Plot 123), but is 15 F hotter than the adjacent fluid. The highest HL

Conductivity Probes indicate dry conditions. The Reactor Vessel Conductivity Probes indicate intermittent

wetting while the CP below the HPI nozzle shows continuous wetting. The Reactor Vessel upper plenum fluid,

like the upper HL fluid, is left superheated as primary saturation temperature decreases (Plot 111).

For the first time in the test, the RV upper plenum fluid temperature exceeds the other RV fluid temperatures.

The SG Secondary fluid temperatures respond to the increased SG heat transfer activity. The SG Secondary

pressure increases to 1100 psia as the simulated steam dump valve chokes (Plot 1). The vapor region

Secondary temperatures follow this saturation temperature increase (Plots 192 and 193). The SG Secondary

pool temperatures decrease as feed is re-introduced (Plot 191).

By 50 minutes the SG Primary has been refilled to the SG Secondary level (Plot 4) and the condensing surface

is recovered.

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3.7 Hot Leg Refill, 55 to 110 Minutes

At 55 minutes the SG Primary condensing surface is totally re-wetted (Plot 4) and the Boiler-Condenser Mode

of heat transfer is extinguished. The Steam Generator heat transfer drops to zero (Plot 19). The SG Secondary

pool temperatures drift downward toward 250 F (Plot 191). The SG Secondary vapor temperatures parallel

the (imposed) Secondary saturation temperature decrease, and abruptly decrease with the Primary SG

temperatures as they de-superheat upon refill (Plots 191 and 193).

Post-BCM (Boiler-Condenser Mode) refill begins with 0,08 Ibm/sec excess of HPI over the leak flow (Plot 17).

HPI cooling is sufficient to condense the generated core steam, thus the Primary repressurizes only mildly,

- 300 psi/hour (Plot 1). The HPI flowrate decreases correspondingly (Plot 17), from 0,15 to 0,11 Ibm/sec. The

Cold Leg temperature distribution indicates a generally fluid stratification (Plot 26), the temperature gauge

CLTC04 just upstream of the HPI discharge point remains at the HPI fluid temperature of 90 F, for almost an

hour. The downcomer and core inlet fluid temperatures gradually cool down, reaching 400 F by 100 minutes

(Plots 111 and 121). With increasing pressure and decreasing leak fluid temperature, the leak flowrate

increases from 0,07 Ibm/sec to 0,09 Ibm/sec by 100 minutes (Plot 17). Thus the excess of HPI over leak flow

decreases from 0,08 Ibm/sec to 0,03 Ibm/sec at 100 minutes (Plot 17). The System refill rate decreases from

40% (of total system volume)/hour, to 25%Ihour at 100 minutes (Plot 105). The HL refill rate is roughly 2/3

ft/min (Plot 4).

During refill the core outlet and W fluid temperatures follow saturation, the RV upper plenum fluid slowly desuperheats (Plot 111). The RV Conductivity Probes indicate intermittent wetting (Plot 112). The HL fluid

successively cools to saturation temperature with the passage of the liquid level. The HL CP's similarly indicate

wetting in succession (Plot 123). The Hot Leg metal at 66' (Plot 124) remains at -575 F until rewetted with HL

level rise. The upper SG Primary fluid temperatures, like those of the HLUB upstream, successively approach

to saturation as they are wetted (Plot 131); the lower SG Primary fluid temperatures are roughly constant at

300 F. The Surgeline metal is approximately 50 F subcooled (Plot 163) reflecting Surgeline heat losses; the

PRZ fills to -13' with gradual repressurization during system refill (Plot 4).

Scheduled 1.5 standard cubic feet NCG (Noncondensible gas) additions to the RV Lower Plenum at 73 and

130 minutes (Plot 16) perturb system conditions but have no major impact on the transient.

At 105 minutes the HLUB upstream piping has refilled to the spillover elevation. Spillover circulation ensues

and the primary flowrate peaks at 7% (Plot 9). The SG is immediately recoupled, and the secondary flowrates

increase to 5% of full flow (Plot 12). The SG heat transfer peaks at 2 Y20% of full power (Plot 19), and the

Secondary pressure increases momentarily by 70 psia (Plot 1). Spillover circulation generally contracts and

subcools the Primary System fluid.

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The primary pressure falls from 930 to 750 psia (Plot 1). The HL upstream level briefly subsides below the

spillover elevation, then both the upstream and downstream HL piping fill (Plot 4). The Pressurizer empties

with Primary depressurization (Plot 4). The average Primary System fluid specific energy decreases from 445

to 400 BTU/bm. HPI fluid is swept into the Downcomer region by forward loop flow; Temperature gauge

CLTC04 upstream of the HPI point increases in response to the warmer upstream CL and SG outlet fluid,

CLTC05 downstream of the HPI point cools toward 200 F (Plot 26). The lower Downcomer and Core Inlet fluid

temperatures are similarly decreasing (Plots 111 and 151). The core outlet fluid is subcooled for the first time

since test initiation. This cold fluid also affects the HL temperatures (Plot 121), abruptly cooling the HL by -100

F starting from the bottom of the HL.

3.8 System Refill, 110 Minutes and Beyond

At 112 minutes the HL-HPV discharge flowrate abruptly increases to 0,025 Ibm/sec (Plot 17), signaling the

completion of HL refill as liquid issues from the HPV. The system natural circulation driving force is slightly

negative at that time; this counters the forward-flow tendencies of HPI fluid flowing to the RV leak, resulting

in negligible system flow (Plot 9). The Secondary feed and steam flows subside following spillover circulation

(Plot 12) and the Steam Generator is largely inactive (Plot 19). The Net System energy change is slightly

negative, the major heat removal mechanism is leak-HPI cooling (Plot 19). The System fluid average specific

energy is slowly increasing.

The HPI flowrate slightly exceeds the liquid discharge flowrate from the leak and the HPV (Plot 17). The

Reactor Vessel and Pressurizer are gradually refilled (Plot 4). The Reactor Vessel Conductivity Probes

successively indicate liquid-immersed conditions, starting from the lowest (below the HL nozzle) at 10 minutes

to the highest (above the VV penetration) at 117 minutes (Plot 112). The RPV upper plenum and W fluid

temperatures indicate subcooled conditions from approximately 115 minutes.

At 117 minutes the continued cooling of the RPV and lower HL fluid yield a sufficiently negative system natural

circulation driving head to trigger a brief pulse of reverse loop flow. This pulse is most discemible on the HL

and SG Primary temperature traces (Plots 121 and 131). From then until 3 hours the loop is stagnant and loop

temperatures vary litme. The Core-W-DC flow loop remains active, however. The Core power of 1,6% of full

power (Plot 19) leads to 60 F RV fluid heat up (Plot 111) with 2% of full flow through the W. The VV flow

combines with the HPI from the CL Discharge (Plot 17) and flows either out of the leak or back to the Core

Inlet.

After 3 hours, the RV is full, the PRZ has refilled to 17' (Plot 4), and the Primary system is filled up to 90%. At

this time the HPI simulation is reduced from 2 to 1 scaled pumps, and testing is continued for another 13

minutes. The HPI flowrate decreases correspondingly at 180 minutes, and the leak flow exceeds HPI flow. The

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Primary pressure decreases toward a revised new leak-HPI equilibrium point (Plot 1). The RPV and PRZ lose

inventory (Plot 4), and the Surgeline metal heatup from 365 F to 490 F confirms the PRZ outsurge. The test

is terminated with the HPI-change transient still in progress.

3.9 Synopsis

A 10 cm2 Reactor Vessel leak with 2 HPI's has been tested from loop saturation to Primary refill. A broad range

of system conditions has been encountered. A two-step initiation sequence was used to approximate plant

conditions at saturation.

The System is initially subcooled in forced flow; the SG Secondary is initialized at high pressure and low level.

Two minutes after Data Acquisition System activation (time zero), the core power is adjusted to the scaled

value at the predicted time of loop saturation, The primary flow is transferred from forced to natural circulation,

the 10 cm2 RV leak is activated, the PRZ main heaters are de-energized, and the W is transferred to automatic control.

From 2 to 6 minutes (after DAS activation) the loop flow subsides, then restarts in natural circulation; the

Pressurizer drains; the primary pressure falls, and the HLUB fluid saturates. Saturation coincides with the

second initiation step: The SG Secondary control pressure and level are reset, the Core power ramp is begun,

and HPI is activated.

Although the system is saturated at 5 minutes and primary inventory is decreasing, saturated spillover persists

until 8 minutes. At 8 minutes the HLUB upstream level begins to fall and primary circulation is interrupted.

Steam Generator heat removal is lost, the Primary begins to pressurize, and the Core region fluid begins to

void. This voiding raises the HL level, causing spillover circulation at 10 % minutes. But spillover causes heat

removal in the SG and thus cooling and contraction of the Primary fluid; HL level is again decreased and

spillover circulation is again Interrupted. These periods of spillover circulation occur at 10 /, 16, and 22

minutes. After 22 minutes Primary inventory is sufficiently reduced to preclude further HLUB spillover, and

Primary flow is stalled (flow in the core-W-Downcomer loop remains active).

From 22 to 35 minutes the Primary re-pressurizes mildly and Primary inventory continues to decrease. At 35

minutes the SG Primary liquid level drops below the Secondary level, exposing a condensing surface and

triggering the BCM. The Primary is rapidly depressurized, the lower Primary elevations are largely quenched

and refilled, and system refill begins at 40 minutes. The Steam Generator condensing surface is re-wetted by

55 minutes and system refill slows from 40% (of total volume) per hour to 25% per hour. The Primary repressurizes gradually during post-BCM refill. Upper-elevation (superheated) fluid and metal temperatures

remain virtually constant until quenching starts by the rising liquid level.

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Finally at 105 minutes the HLUB upstream piping has been refilled to the spillover elevation and primary

circulation restarts. The Primary is rapidly depressurized and generally cooled and refilled by this spillover

circulation. After the HL refill, the primary flow stalls, however the HPI cooling of the core region and the lower

HL fluid density cause a flow-retarding buoyant force.

By 180 minutes the RV is refilled, and the Primary is 90% full of liquid. The Pressurizer level is 18' and is still

increasing. All Primary components other than the PRZ are totally filled, subcooled, and at roughly constant

temperatures. The natural circulation in the Primary loop has not restarted. A brief HPI-simulation change is

appended to the test, then testing is terminated after 193 minutes.

4 RELAP5 MOD 3.2 Analysis of Test 1605AA

4.1 Code Description

The code used for the assessment calculations described by this report is the Mod3.2 version of RELAP5. This

code has been developed within the USNRC Code Assessment and Maintenance program (CAMP) and is

the internationally well known and state-of-the-art best-estimate thermal hydraulics code systems for the

analysis of reactor transients. It is based on a non-homogeneous non-equilibrium model of a one dimensional

two phase flow system. The code solves basically six field equations for the steam-water system including lots

of constitutive models and correlations. The code also can handle non-condensables and other media. It uses

partially implicit numerical schemes to achieve a high calculational speed. The code version used for the

reported analyses was implemented under UNIX operating system on an IBM RS-6000 Workstation.

A comprehensive description of the code is given in Ref. 141

4.2 Modeling Description

Figure 4.1 shows the nodalization to simulate the GERDA Test Facility and test 1605AA with the RELAP5

code. The model is geometrically based on an RELAP4 MOD 6 (BBR Version) model which originally was used

in the eighties for Pre- and Posttest calculations of the GERDA tests however grossly reworked with respect

to discretization and simulation details. The model consists of all major parts of the primary and secondary side

of the test facility, in total of 77 RELAP components with 168 hydrodynamic Volumes, 171 Junctions and

Valves and the Heat Structures adjacent to the piping and Volumes. A complete listing of the base case input

set is listed in Appendix B.

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The simulated sections of the Test Facility include the reactor vessel and core region, the pressurizer, the cold

leg and hot leg, the 'main coolant pump' and the 19 tube steam generator model. The core area of the RPV

is represented by a pipe component subdivided in 6 Volumes, the lower 4 Volumes corresponding to the

heated region containing 4 Heat Structures which simulate the three core simulator heaters. The upper 2

Volumes are not heated (Figure 2.7). The upper plenum and reactor vessel head are composed of two

Branches and a Single Volume. GERDA's lower plenum is simulated with a Branch and a Pipe. This Pipe

simulates the 4 small inlet pipes of the Test Facility's lower plenum.

The pressurizer model is based on the nodalization scheme developed for an ABBR RELAP5 MODI transient

analysis model for the KMK plant and contains a pipe with a subdivision into 10 Volumes.

The head losses for the Main Coolant Pump simulation in GERDA are modeled with an upwards flowing

Branch Volume and a Single Volume connected by a Valve component which is opened for natural circulation

situations and in parallel to this valve a Time Dependent Junction to simulate forced flow situations, followed

by a downward slanting Branch volume.

The most critical aspect of the GERDA model is the Steam Generator. The prototype IEOTSG Steam generator design, based on a license by Babcock & Wilcox, differs considerably from that of other vendors such as

Combustion Engineering (CE), Siemens KWU or Westinghouse which employ a U-Tube type design. The

OTSG is a counterflow steam generator which uses straight tubes. It is shown in Figure 2.3. The Hot and Cold

Legs also differ markedly from U-Tube SG design PWR. The hot leg geometry includes a very tall vertical

section which leads to an inverted U-bend and connects to the upper plenum of the OTSG (HLUB design) The

primary fluid is distributed into more than 16000 tubes and unified at the bottom of the SG in the lower plenum.

From there two Cold Legs connect to the Reactor Pressure Vessel, each fumished with one Main Coolant

Pump similar in design to CE plants of the US. In the GERDA Test Facility two hot legs of the two SG loops

are lumped into one loop thus lumping also the 4 cold legs into one.

To model the behavior of the OTSG is a quite demanding problem because of the complete spectrum of heat

transfer phenomena arising between the tube walls and the secondary coolant (Ref. /51,/61,/7/). In the bottom

region, heat transfer is to a subcooled liquid, then further up the tubes to a saturated liquid, and finally at the

top to a superheated steam. Also the OTSG heat removal rate is very sensitive to the secondary-side liquid

level, because the more inventory is present the more tube surface area is covered which can effectively

transfer heat through boiling which is the most prominent heat transfer mechanism. As the liquid inventory and

the length of the heat transfer regimes strongly influence the actual SG power, a good simulation of OTSG is

a subject of thorough nodalization planning. In the past, several computer codes introduced so called 'moving

boundaries' in OTSG simulations to overcome these problems. RELAP, however, is a discrete volume

boundary type of code. It has some nice features to deal with discrete levels (e.g. in PRZ modeling) like vertical

stratification or thermal front tracking which, however, cannot be applied here. In OTSG modeling a coarse

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nodalization crates discrete jumps in overall heat transfer, which causes the system to be even more sensitive

to the secondary fluid inventory. This can lead to an unstable system. Increasing the number of axial nodes

to create finer mesh intervals helps keep the system from oscillating wildly, provided these intervals are not

too small, which again leads to instability. One economic aspect also has to be considered: fine discretizations

tend to produce large computing efforts. An optimum can be found through sensitivity studies which have been

done in the past very extensively and will not be reported here.

The GERDA SG model is based strongly upon a KMK model developed for RELAP5 MOD1 (ABBR Version)

and is modeled for the MOD 3.2 version as two concentric pipes divided axially into 52 subvolumes, one for

each foot in length of the original vertical pipe. The inlet and outlet plenum is modeled as a Single Volume at

the top and a Branch at the bottom. For the RELAP5 model the hexagonal arrangement of the GERDA-SG

shell was modeled by a circular shell with the same cross-sectional area and height as the original test

arrangement. The primary side pipe is connected to the secondary side pipe by a Heat Structure with original

heat transfer areas which simulates the primary side tube walls and provides the heat flow from the primary

side to the secondary coolant The Feedwater and AUX Feedwater systems parts are simulated by Time

dependent Volumes, Time Dependent Junctions, Valves, a Single Volume and a Branch. The Feedwater is

simulated for the purpose of simplification to enter directly into the bottom of the SG. Correspondingly the

steam leaves the secondary side also simplified directly at the top. The original shell region of the prototype

SG and the Feed Water inlet Downcomer is not simulated, because the influence on the LOCA transient is

negligible in this case.

4.3 Conditioning Calculations

4.3.1 Steam Generator Steady-State Performance

The proof of quality of the input model and the stability of steady state performance especially of the OTSG

model was achieved by a lot of conditioning calculations which have been performed in advance of the post

test analyses. Some of them and the main results will be presented here.

Four separate calculations at steady state conditions were undertaken using a standalone RELAP5 input deck

to test the performance of the GERDA-SG model before an integral model was tested. The initial conditions,

temperatures, pressures, and mass flows were changed in each case to reflect the different power levels in

the GERDA steam generator during steady state conditions. Testing standalone models to insure a correctly

functioning SG is critical to the integral model, because without proper heat removal the overall system model

will not achieve a steady state condition. The SG is as mentioned above the most crucial and complex part

of the overall system.

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Using known temperature distributions (from the old RELAP5/MOD1 inputs) for the KMK-SG model at 100%,

65%, 45%, and 15% total power and flow rates from GERDA steady state data, the initial conditions for the

RELAP5/MOD3.2 GERDA-SG model were developed. For the KMK-SG a set of steady-state and transient

measurements collected during start-up of the plant exist for comparison, see Tables 4.1 - 4.4. These values,

due to the measuring techniques used, have an uncertainty of 3 K for the saturated region and -6 K for the

superheated region, which stems from an occasional water drop hitting the thermocouple causing an erroneous reading.

All of the test calculations were run up to 200 s to achieve a complete stationary, steady-state thermal

hydraulic condition. In addition to the prototype data mentioned above, in Tables 4.1 -4A comparative values

are given of the GERDA facility, prior computer models used for design and analysis and the RELAP5/MOD

3.2 results for GERDA.

The general result of these exercises is that for the 100% SG-Power case stable conditions are obtained after

a relatively short period. The data of the different sources compared in the Tables 4.1 - 4.4 are all relatively

similar, with the exception of the SG inventory for which the RELAP5/MOD 3.2 GERDA model predicts values

which are closer to the GERDA test data than the predictions of both older models and prior computations

(Figure 4.2). The variation comes from the different geometries and from the extrapolated error going from 19

tubes to 16000. The RELAP5/MOD3.2 model simulates a circular outer shell while the actual GERDA facility

SG shell is hexagonal. Steam superheat is about 2 K less than GERDA measurements and plant data but are

2 to 4 K better compared to the older calculational data which illuminates the efforts in code development since

then (Figure 4.3).

For the 65% SG-Power case the secondary side mass inventory again is less than older calculational data

But dose to GERDA data. Steam superheat only differs about I K from GERDA data. For the 45% and 15%

SG-Power level the secondary side steady-state mass inventory is very similar to known data, except that for

the 15 % Power Level no GERDA data was available. It is noteworthy that the steam superheat is very close

to the prototype data and only deviates by about I K from the GERDA data, which is a very good result with

respect to the low rated power levels we have to deal with in the LOCA transient.

4.3.2 GERDA-1 Loop Model Steady.State

With a high degree of confidence in the steam generator moders proper functioning, it was integrated into the

full RELAP5 model of the GERDA facility. The nodalization scheme can be seen in Figure 4.1 of Appendix A..

The model was then run at 7.5% full power for one SG till steady state conditions were achieved. Since the

KMK plant has 2 SGs the GERDA data must be compared to the 15% full power data of the KMK plant By

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multiplying the RELAP5 GERDA-Model results by the scaling factor (S = 1686) the appropriate values for

comparison will result The results of the integral run can be seen in Table 4.5 in appendix A. The computed

data compares quite well as shown in the table.

From this steady-state conditioning calculations some modifications to the boundary conditions in the data set

of the GERDA model have been made in order to achieve a steady state faster and in order to hit the initial

starting parameters of the test.

4.4 Calculational Procedures

Prior to the Post test calculation steady state runs were performed with the rated power level of the test which

was 5.25 %. The Post Test calculation was started with the initial parameters evaluated in these steady state

calculations. Time zero in the test, which is 1024.12 on 12-April-83 is time zero of the calculation. This implies

that the model is run at steady state conditions for 145 s with forced coolant flow modeled by the Time

Dependent Junction 907. At 145 s the coolant flows was forced to cast down to zero flow in 5 seconds while

opening Valve 906 to allow for natural circulation flow.

The PRZ main heaters and the PRZ guard heaters are not simulated, so no actions are taken here.

The leak of 10 cm2 at the lower plenum of the Reactor Pressure Vessel modeled by Valve 905 is opened at

145 s. The rated core power is started to ramp down to 4,4 % of full power simulating a post shutdown situation

at the time the leak is opened. At 355 s, when the LOCA signal 'System Pressure < 117 Ba? is generated the

core power is continually ramped down based on the test data simulating decay heat.

From time zero to the time of the LOCA signal (355 s) a secondary side pressure control of 79 bar was

maintained at a steam generator secondary water level which corresponds to non-LOCA post-trip situations. The steam generator is being fed in this time span by two Aux-Feedwater Pumps. At 355 s, upon the

LOCA signal (which is the approximate time of loop (HLUB) fluid saturation) the SG Secondary set points

were realigned to obtain 48 bar (700 psia) steam pressure and (Post-LOCA) level control of 8.4 - 9.0 musing two simulated AFW pumps. Additionally two simulated HPI pumps were activated to feed into the

Cold Leg Discharge (CLD) piping.

The original KMK SG level control scheme feeds to 8,14 m, then steams down to 7,62 m without feed, in a

repetitive band-control fashion. Additionally, during the GERDA test feedrate adjustments were made to

simulate prototypical AFW head-flow characteristics. In the calculation these controls are simulated as

automatic. The reason for the difference of the steam generator level control setpoints between test and

calculation was an unsufficiently low heat transfer rate of the model at the lower SG secondary side water

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level. To correct this underprediction, the level setpoints were increased by about 0,8 m to the ones stated

above.

As an operator action at 32 minutes the High Point Vent (HPV) is opened like in the test and the SG Secondary

is depressurized to obtain the prototypical 50 F/hour (28 K/hour) cooldown.

Compared to the test RELAP5 predicted a leak mass flow which roughly was 25% to high in situations with

considerably subcooled fluid. Therefor the 10 cm2 RPV Bottom leak is modeled and simulated without any

cross section reductions of the leak area up to 44 minutes into the transient which roughly is the time refill

begins. At that time the leak mass flow in the calculation was reduced to the leak mass flow measured in the

test, which is about 75% of the leak mass flow RELAP originally predicts.

In the test as a scheduled action, 1,5 standard cubic feet NCG (Noncondensable gas) were added to the RV

Lower Plenum at 73 and 130 minutes, which perturbed system conditions but had no major impact to the

transient. The NCG addition was not simulated in the Post-Test calculation.

The test basically ended at 180 min when the primary system was filled up. The calculation ended at 200 min

but comparisons to the test only were made up to 180 min (10000 s).

4.5 Results of Post-Test calculations and Comparison to the Test

The overall system responses and the most prominent parameters are shown in Figures 4.4 -4.8. In Table

4.6 the timing of major phenomena as computed is compared to the test. Almost all of these phenomena are

predicted well in sequence and timing. The most important phenomenon is the time when the LOCA signal is

generated after the leak is opened and subsequently, when the LOCA actions are initiated, the onset of BCM,

the duration of BCM and the refill of the Primary.

At 145 s the transient is initiated by opening the leak Valve 905. The RELAP5 system pressure at that time

is a little bit higher than in the experiment (Fig. 4.4). The primary forced circulation was tripped by Time

Dependent Junction 907 and natural circulation was allowed by opening Valve 908. The loop flow subsides

for a short time and then recovers till the loop circulation is interrupted first at about 480 seconds (Fig. 4.10).

Saturated HLUB spill over causes intermediate loop flow. At about 17 minutes the flow stagnates and after

a last short spill over at 22 minutes and further the flow stagnates totally till the refill of the HL.

The Pressurizer is drained by 210 seconds in the test (Plot 4) and at 280 seconds in the calculation. Due to

the leak the system pressure falls rapidly reaching 1700 psia (117 bar) by 330 seconds in the test (Plot 1)

and 356 seconds in the calculation (Fig. 4.4). Saturation is reached in the Primary at the same time. The LOCA

NRC-C03.OC - A&r.Ws
A BB ABB Reaktor GmbH GBRA 043 970 Blatt / Page 24

signal activates the SG secondary control pressure of 48 bar and high SG level control setpoints. HPI is

activated (Fig. 4.11) and the core power ramp is begun. In Figure 4.9 the core power as measured in the test

is shown. The core power history from the test is input into the heater rods simulating the core in the RELAP

analysis. The resultant heat flow from the heater rods to the coolant as calculated is shown in the same figure.

At about 2000 s when the operator action, venting of HLUB and initiating cool down with 28 K/h, becomes

effective the BCM, which starts at about the same time is substantially enhanced, the system experiences an

immediate and significant depressurization and cool down. This results in a considerable power peaking and.

heat flow from the core to the coolant (Fig. 4.9). In the transient phases before the onset of BCM the short

pulses of saturated spill over flow in the HLUB result in peaks of heat flow from core to water.

Although the system is saturated at about 5 minutes and the primary inventory is further decreasing, due to

the leak flow which is still much higher than the HPI flow (Fig . 4.12), saturated continuous spillover persists

until 8% minutes (Fig. 4.10). At that time the HLUB upstream level begins to fall and primary circulation is

interrupted for the first time and only a short period. The same situation can be observed in the test. The result

of this interruption is that the Steam Generator heat removal is lost, the Primary begins to pressurize, and the

Core region fluid begins to void. This voiding raises the HL level again, causing further spillover circulation

cycles fill the mass loss in the Primary is so big that no further spillover can persist for a longer time frame (Fig.

4.11). Each of these spillover cycles cause heat removal in the SG and thus cooling and contraction of the

primary fluid. These periods of spillover circulation occur in the test as well as in the RELAP calculation as

can be seen from Figures 4.4 and 4.5. After about 22 minutes primary inventory is sufficiently reduced both

in the test and in the prediction to preclude further HLUB spillover, and primary flow is stalled. Despite stalled

flow in the loop the internal loop in the RPV via the W is still very active as shown in Figure 4.14.

The RELAP prediction of the W flow especially from 3000 s to 6000 s seems to be much lower than the

measured W flow. The VV flow however is not a continuous one and plots tend to smooth by graphical

integration. For that reason the W flow as calculated by RELAP was integrated and compared to the integral

W mass flow from the test which was available as a calculated test parameter. The result is depicted In

Figure 4.15. It is demonstrated that at least from 2000 s to 6000 s the W mass flows integrally compare very

well.

From 22 to 35 minutes the Primary re-pressurizes mildly in the test and some more in the calculation (Fig. 4.4).

This difference is caused by a too low heat removal in the RELAP SG during that phase as compared to the

test At 35 minutes (2100 s) both in both the test and in the calculation the SG primary liquid level drops below

the secondary level, which very well can be seen from Figure 4.8, exposing a condensing surface and

triggering the BCM. The Primary is rapidly depressurized, HPI mass flow, within a short time period jumps to

a new equilibrium flow rate (Fig. 4.11), the leak mass flow decreases due to the depression and the lower

primary elevations are largely quenched and refilled. This can well be seen by the integrated mass flows of

leak and HPI from Figure 4.13. Figure 4.8 additionally shows that the reactor vessel upper plenum drained

NRC. oC A!. MOrTits
A B B ABB Reaktor GmbH GBRA 043 970 Blatt I Page 25

completely to a minimum of about- 2 m (The reference elevation of 0 is the center of the W, Fg. 2.7) which

is about I m above the GERDA core simulator and is still above heated core of the prototype plant. In both

the test and in the calculation the system begins to refill at about 40 minutes.

The comparison between the calculated refill rate to the test data also can be observed from Figure 4.7. The

refill rate of the HL compares very well to the test, however the refill rate as calculated is retarded grossly by

about 500 seconds, but reaches the modeled spillover level earlier than in the test (Fig 4.6). This delay of refill

is caused by a too low HPI flow (Fig. 4.11) in the timeframe from 2000 s to 3500 s as compared to the test,

whereas the leak flow of calculation and test is pretty much the identical (Fig. 4.13). This deviation of HPI flow

can be explained by a lower heat removal capability of the RELAP5 SG as compared to the GERDA SG, with

the consequence that the calculated system pressure is above the pressure measured in the test (Fig. 4.4).

During the refill the Steam Generator condensing surface is re-wetted after about 13 minutes into the BCM,

which causes the refill of the SG tubes and of the downwards bound HL to slow. This effect is more pronounced in the calculation than in the test (Fig.4.7). At 6000 seconds into the transient the difference in time

between test and calculation of reaching the same collapsed water level (e.g. the spill over elevation) is about

1000 seconds.

In the test at 6300 seconds (105 minutes), the HL upwards bound piping has been refilled to the spillover

elevation and primary circulation restarts. This effects the W flow and the system pressure. The Primary is

rapidly depressurized at 6300 seconds (Fig. 4A) and the W flow decreases (Fig. 4.14). The RPV is generally

cooled very effectively (Fig 4.6) by this spillover circulation. The RELAP calculation predicts a fill up of the HL

200 s in advance to the test (Fig. 4.6). The subsequent core cooling is only half as effective as seen in the

test. The reason is that, triggered by the fill up, RELAP predicts severe flow oscillations with parts of reverse

flow in the loop (HL) and in the RPV and a significant increase of W flow (Fig. 4.14,4.21). This big VV flow

causes the observed increase of lower and upper core temperatures at about 6200 s, shown in Figure 4.6.

This increased VV flow of the RELAP calculation also can be seen in Figure 4.15

In the test, after HL refill, at 112 minutes (6720 s) the circulation of primary flow stalls, and W flow increases

very rapidly (Fig. 4.14,4.15). The core region is only cooled via HPI and the internal RPV circulation flow. The

core exit fluid temperature rises and the lower RPV plenum temperature falls (Fig 4.6). At 117 minutes (7000

s) the continued cooling of the RPV and lower HL fluid yield a sufficiently negative system natural circulation

driving head to trigger a brief pulse of reverse loop flow. This pulse however is not seen very well in the test

data but is reflected in the temperature readings shown in Figure 4.6. In the RELAP calculation on the contrary

a negative pulse of reverse flow caused by a negative driving head is not observed.

After the reversed flow has ceased until the end of the transient the loop is stagnant and loop temperatures

vary little. The Core-W-DC flow loop remains active (Fig. 4.14) both in the test and the calculation.

NWC,.OC ..- .•&fTs
A BBG ABB Reaktor GmbH GBRA 043 970 Blatt I Page 26

The phenomena observed in the test during 6000 s and 8000 s are not too well predicted by the RELAP

calculation. Very well predicted however is the final condition of the system at the end of the transient (10000

s), the trend in system pressure, the leak and HPI mass flow (see described modifications), the W flow and

the short period of circulation flow when the Hot Leg is filled up to the spillover level at 6100 s, at 6400 s and

later at about 7000 s.

In the RELAP calculation the first fill up of the Hot Leg causes flow oscillations with the effect of a triggered

VV flow. For a short time the HL level decreases again and backs up to the spillover elevation at 6400 s

triggering again an immediate flow from the Hot Leg to the SG primary tubes, accompanied by severe flow

oscillations (Fig 4.21). The fluid spilled over at 6400 s from the Hot Leg to the SG is saturated and has a much

higher temperature than the fluid on the secondary side (Fig. 4.16). Nevertheless RELAP calculates a significant decrease of secondary side pressure at 6400 s which is strange. The opposite should be expected when

hot water flows into the SG tubes. It should be mentioned that no feedwater was injected into the Secondary

which could result in a sudden depressurization. The reason for this depressurization actually is a negative

heat transfer from the secondary to the primary side as calculated by RELAP at 6400 s (Fig. 4.17). The root

cause is not a flow of primary coolant backwards from the Cold leg into the bottom of the SG which also could

result in a negative heat flux. Digging deeper into this phenomenon it can be found that the calculated

negative heat flux causing the problem is mostly prominent in SG levels 19 through 36 (Fig. 4.18). The reason

is a big secondary side heat transfer coefficient in that time frame between 6400 s and 6500 s as shown in

Figure 4.19 for node 23 (primary noding, corresponding to node 30 on the secondary side). The reason why

especially in that time frame such a big heat transfer is computed are severe flow oscillations that occur on

the secondary side of the SG. From Figure 4.20 it is leamed that before 6400s the Flow Regimes oscillate

between Mist-Post-CHF and Mist-Pre-CHF with a relatively stable phase between 6400 s and 6500 s in the

Annular-Mist regime. These instabilities at the SG secondary side are grossly responsible for the observed

unrealistic heat transfer.

At about 6800 s, however, when the HLUB is filled from both sides, a considerable (positive) circulation flow

is induced, again triggering a positive step of W flow and causing a secondary pressure peak which at that

time is expected and predicted well. This peak was also experienced in the test (Fig. 4.5). At about 6900 s

of the calculation the primary flow again destabilizes and oscillates heavily causing considerable pressure

spikes and substantial condensation effects in Volume 280 (RPV top plenum). This subsequently causes an

unphysical immediate fill up of RPV top plenum at 116 min (Fig. 4.8). Consequently an instant drainage of the

HLUB below the spill over elevation (Fig. 4.7) results. For another 500 s the circulation stalls again (Fig. 4.21).

At 7500 s finally the HLUB is filled again, and natural circulation starts causing the second pressure peak on

the Secondary. The Primary re-pressurizes gradually during post-BCM refill, both in the test and the calculation.

,aC-~OU= -AAM.MrsI~
A l I M EPABB AB Reaktor ektrGb GmbH GBRA 043 970 Blatt / Page 27

5 Conclusion

The GERDA Test Facility simulates post SBLOCA thermal-hydraulic events in OTSG plants of B&W 205

design. The integral (composite) Test 1605AA which features a complete sequence of a 10 cm2 Reactor

Vessel Leak transient conducted on Apnl 12th, 1983 was used as data basis for assessment calculations with

RELAP5/MOD3.2. The results of these post test calculations were compared to the test data. The comparison

presented in this report has shown that in general the majority of the important phenomena are predicted well.

In detail it was found that the OTSG heat transfer capability was less than measured and the discharge leak

flow rate between 2600 s and - 8000 s was about 25% to high compared to measured data. The other

problems found analysing the RELAP results stem from flow oscillations which mostly are caused by a poor

prediction of the transition from stagnant flow to natural circulation after refill of the primary system. The severe

flow oscillations observed cause additional second order problems like pressure spikes, condensation in the

RPV and triggering W flow. These induced problems subsequently have immediate and significant influence

on the overall system behaviour. Another problem was identified in the heat transfer on the secondary side

of the Steam Generator. In the present case instabilities in the flow regime selection results in negative heat

transfer. Once the observed disturbances are mastered, however, the comparison to the test shows that

RELAP predicts a system behaviour which is very close to the tested scenario.

It was concluded from the comparison that the predictability especially for the BCM (Boiler-Condenser-Mode

of Heat-Transfer) in general is fairly good. OTSG performance, especially the heat transfer models and logic

for the selection of heat transfer regimes should be a target for further fine tuning and improvements. The refill

problem and the root cause for the observed deficiencies and the flow oscillations should be eliminated.

WaC40 - M-OtWTS
A BB ABB ReaktorGmbH GBRA 043 970 Blatt Page 28

6 References

/l/ G. Ahrens, G. Haury, K. Lahner, A. Schatz

Versuchsanlage GERDA f~r DWR mit Geradrohrdampferzeuger,

Atomwirtschaft, Atomtechnik, Nov. 1983

/2/ G. Ahrens, G. Haury, K. Lahner

BBR -Versuchsanlage GERDA zur Untersuchung von KOhlmittelveriustst6rfAllen

mit kleinen Lecks im Prim~rkreis

Jahrestagung Kemtechnik '84, Tagungsbericht ISSN 0720-92207

/3/ R. Salm, S. Schwarz, D. Steinkamp

Ergebnisse der NotkOhlversuche zu Idelnen lecks an der BBR - Versuchsanlage GERDA

Jahrestagung Kemtechnik '84, Tagungsbericht ISSN 0720-92207

141 Idaho National Engineering Laboratory

RELAP5/MOD3 Code Manual

NUREG/CR-5535 INEL-95/0174 Vol. I-VII

/5/ Yassin A. Hassan (B&W)

Simulation of a 19-Tube Integral Economizer Once-Through Steam Generator Experiment

Using the TRAC-PF1 Code

Trans. Am. Nucl. Soc. ISSN 0003-018X (1985) v. 49, p 448-450

Annual meeting of the American Nuclear Society, Boston, MA (USA)

/6/ Yassin A. Hassan (Texas A&M University)

Assessment of boiling heat transfer correlations for Once-Through Steam Generators

Nuclear Technology, Vol. 81, June 1988, pp 446-450

/7/ Yassin A. Hassan, Omar Rais (Texas A&M University)

Two-Phase Flow Interfacial Drag for Once-Through Steam Generators

Nuclear Technology, Vol. 95, July 1991, pp 77-86

NW,= .DO - k. rr
A R I ABB Reaktor GmbH GBRA 043 970 Blatt I Page 29

7 List of Figures and Tables

Figures

Figure 2.1 View of B&W 205-FA Design IEOTSG Plant

Figure 2.2 View of B&W 177-FA Design OTSG Plant

Figure 2.3 Characteristic Data of OTSG type 177 and 205

Figure 2.4 GERDA Test Facility

Figure 2.5 OTSG 19-Tube Bundle Test Section

Figure 2.6 Comparison of Full-Size 205-FA Plant OTSG to 19-Tube OTSG in GERDA

Figure 2.7 Comparison of Full-Size 205-FA Plant Reactor Vessel to GERDA Reactor Simulation

Figure 2.8 Comparison of Full-Size 205-FA Plant Cold Leg to GERDA Cold Leg

Figure 2.9 GERDA Instrumentation, Overview

Figure 2.10 GERDA Instrumentation, Details

Figure 2.11 GERDA Instrumentation, Pressure Difference Measurements

Figure 4.1 GERDA Nodalization Scheme for RELAP 5MOD3.2 Calculations of Test 1605AA

Figure 4.2 OTSG Secondary Side Inventory as Function of Rated Power

Figure 4.3 OTSG Secondary Steam Superheating as Function of Rated Power

Figure 4.4 Comparison of Measured and Calculated Primary Pressure

Figure 4.5 Comparison of Measured and Calculated SG Steam Pressure

Figure 4.6 Comparison of Measured and Calculated Core Intel and Outlet Temperature

Figure 4.7 Comparison of Measured and Calculated Hot Leg and SG Primary Water Level

Figure 4.8 Comparison of Measured and Calculated SG Secondary and RV Water Level

Figure 4.9 Comparison of Measured and Calculated Core Power

Figure 4.10 RELAP5 MOD 3.2 Prediction of Mass Flow in HLUB

Figure 4.11 Comparison of Measured and Calculated HPI Mass Flow

Figure 4.12 Comparison of Measured and Calculated Leak Mass Flow

Figure 4.13 Comparison of Measured and Calculated Integrated Mass Flow of HPI and Leak

Figure 4.14 Comparison of Measured and Calculated Vent Valve Mass Flow

Figure 4.15 Comparison of Measured and Calculated Integrated Vent Valve Mass Flow

Figure 4.16 Comparison of Measured and Calculated Temperatures in HLUB Downwards bend Piping

Figure 4.17 RELAP5 MOD 3.2 Prediction of SG Power, 5000 s - 8000 s

Figure 4.18 RELAP5 MOD 3.2 Prediction of SG Power, Details from 6200 s -6800 s

Figure 4.19 RELAP5 MOD 3.2 Prediction of SG HT Coeff. in Prim. Node 23, 6200 s -6800 s

D:•wTOAiMO9RMEAWR=DOC CA9 - .Or*Jiis
A BB ABB Reaktor GmbH GBRA 043 970 Blatt I Page 30

Figure 4.20 RELAP5 MOD 3.2 Prediction of Secondary Flow Regimes, Details form 6200 s - 6800 s

Figure 4.21 RELAP5 MOD 3.2 Prediction of HLUB and RPV-Downcomer Mass Flow Rates,

5000 s - 8000 s

Tables

Table 2.1 Instrumentation used in Composite GERDA Test 1605AA

Table 3.1 Detailed Sequence of Events of Composite GERDA Test 1605AA

Table 4.1 OTSG at 100% Rated Power, Comparative Data

Table 4.2 OTSG at 65% Rated Power, Comparative Data, RELAP, KMK and GERDA

Table 4.3 OTSG at 45% Rated Power, Comparative Data, RELAP, KMK and GERDA

Table 4.4 OTSG at 15% Rated Power, Comparative Data, RELAP, KMK and GERDA

Table 4.5 Integral Loop OTSG at 7,5% Rated Power, Comparative Data, RELAP, KMK and GERDA

Table 4.6 Timing of Major Phenomena, Comparison of RELAP5 and GERDA

Original Data Plots from GERDA Composite Test 1605AA

Plot I System Pressure (0 - 60 min, 0- 300 min)

Plot 4 Collapsed Levels (0 - 60 min, 0- 300 min)

Plot 9 Primary Flow rates (0 - 60 min, 0 - 300 min)

Plot 12 Secondary Flow rates (0- 60 min, 0 - 300 min)

Plot 16 Limit Switches of Valves (0 -60 min, 0 - 300 min)

Plot 17 Primary Mass Balance (0 - 60 min, 0- 300 min)

Plot 19 Primary Energy Balance (0 - 60 min, 0 - 300 min)

Plot 26 Cold Leg Temperature (0 -60 min, 0- 300 min)

Plot 102 Saturation Temperatures (0- 60 min, 0 - 300 min)

Plot 105 Liquid Volume (0- 60 min, 0- 300 min)

Plot 111 Core Vessel Fluid Temperatures (0 - 60 min, 0- 300 min)

Plot 112 Core Vessel Conductivities (0 - 60 min, 0 -300.min)

Plot 121 Hot Leg Fluid Temperatures (0- 60 min, 0 - 300 min)

Plot 123 Hot Leg Conductivities (0 - 60 min, 0 -300 min)

Plot 124 Hot Leg Metal Temperatures (0 - 60 min, 0 - 300 min)

Plot 131 SG Primary Fluid Temperatures (0 - 60 min, 0- 300 min)

Plot 132 SG Primary Fluid RTD Temperatures (0 -60 min, 0 - 300 min)

D:VATDWVW18M.AWC.CO1OC (M - M-.HJWTs
A ABRekorGb ABB Reaktor GmbH GBRA 043 970 Blatt/ Page 31

Plot 141 Cold Leg Fluid Temperatures (0 - 60 min, 0 - 300 min)

Plot 151 Down Comer Fluid Temperatures (0 - 60 min, 0 - 300 min)

Plot 161 Pressurizer Fluid Temperatures (0- 60 min, 0 - 300 min)

Plot 163 Pressurizer Metal Temperatures (0 - 300 min)

Plot 171 RVVV (VV) Fluid Temperature (0- 60 min, 0 - 300 min)

Plot 172 RVVV (VV) Pressure Difference (0 - 60 min, 0 - 300 min)

Plot 191 SG Secondary Fluid Temperatures (0 - 60 min, 0 -300 min)

Plot 192 SG Secondary Fluid Temperatures (0 - 60 min, 0 -300 min)

Plot 193 SG Secondary Fluid Temperatures (0 - 60 min, 0 - 300 min)

&.=7&MWOD=5W8O5V4C.-O2.O (31) - AA-00fct~s

A BB ABB Reaktor GmbH

GBRA 043 970 Blatt / Page Al

APPENDIX A

Figures and Tables

OAMTMWOAD1MEMMoWC-oc&O (t) - MA4-OW.,S
ABS ABB RalrGb GBRA 043 970 Blatt I Page A2

Figure 2.1 View of B&W 205-FA Design IEOTSG Plant

KTATeAV51OrMBEAhO"C.OM=O . AM&.trlra
ABBr ABB Rea~ktorGmbH

GBRA 043 970 Blatt I Page A3

Figure 2.2 View of B&W 177-FA Design OTSG Plant

M"O^%MIc.OW aoC&OC- M~orfns
A BB ABB Reaktor GmbH

GBRA 043 970 Blaft / Page A4

IEOTSGDampferzeuger

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Some specific data of

Number of tubes

Length of tubes (m)

Diameter & wall thickness

Coolant flow (kg/s)

Steam flow (kg/s)

Life steam pressure (bar)

Life steam temperature (C)

Steam superheating (C)

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Figure 2.3 Characteristic Data of OTSG type 177 and 205

KTATWW0MI08EA80WC-== - PIA-Dr.Mffs
ABB GBRA 043 970 Blatt I Page A5

ABB Reaktor GmbH

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LPM'MATMWaRD•10IftADMRCa-aJoC - M,.Wr."Ts
A BB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page A6

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AIP ABB Reaktor GmbH

GBRA 043 970 Blatt I Page A7

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NOTE- COMPONENTS ARE DRAWN TO SCALE IN ELEVATION;

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Figure 2.6 Comparison of Full-Size 205-FA Plant OTSG to 19-Tube OTSG in GERDA

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Relap 5Mod3.2 Assessment

GERDA Test 1 605AA, System Pressure. , 18000000.0 1

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GERDA Test 1605AA

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GERDA Test 1 05AA, HL & SG primary .side

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5Mod3.2 Assessment

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GERDA Test 1605AA

150000.0

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GERDA Test 1605AA. HLUB Mass Flow

m

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GERDA lest 1605AA, HPI Flow

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Relap 5Mod3.2 Assessment

GERDA Test 1 605AA, Leak Flow

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200.0

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GERDA "les 1605AA, SG Power

50000,0

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GERDA Tesi 1 605AA. SO Power

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GERDA Test 1605AA. SG Power

15.0

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GERDA -esi 1605AA, SC Power

1.0

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Assessmenf

Dr

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8000.0
Al ABB G GBRA 043 970 Blatt I Page A34

INo Measurement Unit System Instrument Locatlon,ft

I SPPR01 PSIA

2 ISPDP01 PSI

3 SPLV01 PSI

4 SPRT01 DEG F 3 SGP SG PRIMRY 3 RTD FLUID RTD +53.10

5 SPRT02 DEG F 3 SGP SG PRIMRY 3 RTD FLUID RTD +53.10

6 SPRT03 DEG F 3 SGP SG PRIMRY 3 RTD FLUID RTD -2.80

7 SPRT04 DEG F 3 SGP SG PRIMRY 3 RTD FLUID RTD -2.90

8 SPTC01 DEG F 3 SGP SG PRIMRY 2 FTC FLUID TEMP +47.10

9 SPTC02 DEG F 3 SGP SG PRIMRY 2 FTC FLUID TEMP +38.20

10 ISPTC03 DEG F 3 SGP SG PRIMRY 2 FTC FLUID TEMP +35.30

11 SPTC04 DEG F 3 SGP SG PRIMRY 2 FTC FLUID TEMP +17.30

12 SPTC05 DEG F 3 SGP SG PRIMRY 2 FTC FLUID TEMP +8.10

13 SPTC06 DEG F

14 SPTC07 DEG F

15 SPTC08 DEG F

16 SPTC09 DEG F

17 SPTCI0 DEG F

18 SPTC11 DEG F

19 SPTC12 DEG F

20 SPTC13 DEG F

21 SPTC14 DEG F

22 SPTC15 DEG F

23 DCDPO3 PSI

24 DCLV03 PSI

25 DCOR03 LBM/HR

26 SPTC19 DEG F

27 SPTC20 DEG F

28 SPTC21 DEG F

29 SPTC22 DEG F

30 SPTC23 DEG F

31 SPTC24 DEG F

32 SPTC25 DEG F

33 SPTC26 DEG F

34 SPTC27 DEG F

35 SPTC28 DEG F

36 SPPT01 PSI

37 SPPT02 PSI

38 SPPT03 PSI

39 SPPT04 LBM/HR

40 SPPT05 LBM/HR

41 SPPT06 LBM/HR

42 SSTC25 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +49.80

43 SSTC24 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +47.00

44 SSTC23 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +47.00

45 SSTC22 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +44.20

46 SSTC21 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +44.20

47 SSTC20 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +41.20

48 SSTC19 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +41.20

49 SSTC18 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +38.20

50 SSTC17 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +38.20

Table 2.1 Instrumentation used in Composite GERDA Test 1605AA

D.ZATEMWVROt5¶OS1BA8050VtC.OO1D - AM-&rTirs
AIB ABB Rea or GmbH GBRA 043 970 Blatt I Page A35

lNo Measurement Unit System Instrument Location,ft

51 SSTC16 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +35.30

52 SSTC15 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +35.30

53 SSTC13 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +32.30

54 SSTC12 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +29.20

55 SSTC11I DEG F 22 SGS SQ SECOND 2 FTC FLUID.TEMP +29.20

56 SSTC10 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +26.30

57 SSTC09 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +26.30

58 8STC08 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +23.10

59 SSTC07 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +20.10

60 SSTC06 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +17.30

61 SSTC05 DEG F 22 SGS SQ SECOND 2 FTC FLUID TEMP +14.10

62 SSTC04 DEGF 22 SGSSGSECOND 2 FTC FLUID TEMP +11.10

63 SSTC03 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +8.10

64 SSTC02 DEG F 22 SGS SG SECOND 2 FTC FLUID TEMP +4.90

65 SSTC01 DEG F 22 SOS SG SECOND 2 FTC FLUID TEMP +1.50

86 SSDPOi PSI

67 SSLV01 PSI

68 SSDPO2 PSI

69 SSLV02 PSI

70 SSDP03 PSI

71 SSLV03 PSI

72 SSDPO4 PSI

73 SSLV04 PSI

74 SSDP05 PSI

75 SSLV05 PSI

76 SMTC06 DEG F

77 SMTC05 DEG F 22 SGS SG SECOND 25 MTC METAL TC +38.20

78 SMTC03 DEG F 22 SGS SG SECOND 25 MTC METAL TC +29.20

79 SMTC02 DEG F 22 SGS SG SECOND 25 MTC METAL TC +26.30

80 SMTCo1 DEG F 22 SGS SG SECOND 25 MTC METAL TC +20.10

81 RVTC01 DEG F I RV CORE VESL 2 FTC FLUID TEMP -23.70

82 RVTC02 DEG F I RV CORE VESL 2 FTC FLUIDTEMP -19.10

83 RVTC03 DEG F I RV CORE VESL 25 MTC METAL TC -16.00

84 RVTC05 DEG F I RV CORE VESL 25 MTC METAL TC -11.90

85 RVTC06 DEG F I RV CORE VESL 25 MTC METAL TC -9.90

86 RVTC07 DEG F I RV CORE VESL 2 FTC FLUID TEMP -8.30

87 RVTC08 DEG F I RV CORE VESL 2 FTC FLUID TEMP +8.80

88 RVTC09 DEG F 7 RW R.V.V.V. 2 FTC FLUID TEMP +0.60

89 RVTC10 DEG F 7 RW R.V.V.V. 2 FTC FLUID TEMP +0.60

90 RVWM01 KWATT I RV CORE VESL 7 0 POWER [%FP] -13.20

91 RVDP01 PSI

92 RVLV01 PSI

93 RVDP02 PSI

94 RVLV02 PSI

95 RVDP03 PSI 3 RW R.V.V.V. 8 DP PRES.DIFF +0.60

96 RVDP04 PSI

97 RVLV04 PSI

98 RVDP05 PSI

99 RVLV05 PSI

100 RVPR01 PSIA

Table 2.1 Instrumentation used in Composite GERDA Test 1605AA, Continued

MDAT.c•hEMWO 1BIEABO' ,,-OO3.COC . AV-O&.TWs
A BB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page A36

lNo Measurement Unit System Instrument Locatlon~ft

PRDTOI , DEG F 6 PR PRESURIZR 10 DT INSUL DT +1220

102 PRDT02 DEG F 6 PR PRESURIZR 10 DT INSUL DT +27.10

103 PRDT03 DEG F 8 PR PRESURIZR 10 DT INSUL DT +4280

104 PRTC01 DEG F 6 PR PRESURIZR 2 FTC FLUID TEMP +21.90

105 PRTC02 DEG F 6 PR PRESURIZR 2 FTC FLUID TEMP +34.20

106 PRTC03 DEG F

107 PRTC04 DEG F 6 PR PRESURIZR 25 MTC METALTC +18.00

108 PRTC05 DEG F 6 PR PRESURIZR 25 MTC METAL TC +36.80

109 PRTCO0 DEG F 8 PR PRESURIZR 25 MTC METALTC +48.50

110 i PRPR01 PSIA

111 lPRDP01 PSI

112 PRLVOI PSI

113 HPTCOI DEG F 10 HPI HP INJECT 2 FTC FLUID TEMP -999.00

114 CLTC0I DEG F 4 CL COLD LEG 2 FTC FLUID TEMP 4.70

115 CLTC02 DEG F 4 CL COLD LEG 2 FTC FLUID TEMP -4.50

116 CLTC03 DEG F 4 CL COLD LEG 2 FTC FLUID TEMP -0.10

117 CLTC04 DEG F 4 CL COLD LEG 2 FTC FLUID TEMP +1.80

118 CLTCo5 DEG F 4 CL COLD LEG 2 FTC FLUID TEMP -0.50

119 CLDPOI PSI

120 CLLVOI PSI

121 CLOR02 LBM/HR

122 CLDPO2 PSI

123 CLDPO3 PSI

124 CLLVO3 PSI

125 DCTC01 DEG F 5 DC DOWNCOMER 2 FTC FLUID TEMP -3.20

128 DCTC02 DEG F 5 DC DOWNCOMER 2 FTC FLUID TEMP -10.00

127 DCRTOI DEG F 5 DC DOWNC=MER 3 RTD FLUID RTD -20.00

128 DCOR01 LBM1HR

129 DCDP01 PSI

130 DCDP02 PSI

131 DCLV02 PSI

132 VITC01 DEG F 11 VI I-PH VENT 2 FTC FLUID TEMP -999.00

133 V2TC0I DEG F 12 V2 2-PH VENT 2 FTC FLUID TEMP -999.00

134 V2TC02 DEG F 12 V2 2-PH VENT 2 FTC FLUID TEMP -999.00

135 V2TC03 DEG F 12 V2 2-PH VENT 2 FTC FLUIDTEMP -999.00

138 V2TC04 DEG F 12 V2 2-PH VENT 2 FTC FLUID TEMP -999.00

137 V2PR01 PSIA 12 V2 2-PH VENT I P PRESSURE -999.00

138 V2DPOI PSIA

139 V2LV0I PSIA

140 V2DP02 PSIA

141 V2LV02 PSIA

142 V2DP03 PSIA

143 V2LV03 PSIA

144 V2DPO4 PSIA

145 V2LV04 PSLA

145 V2DP05 PSIA

147 V2LV05 PSLA

148 V2RFOI FT"3 12 V2 2-PH VENT 18 VOL NCG VOL -M99.00

149 HLRTOI DEG F 2 HL HOT LEG 3 RTD FLUID RTD 0.00

150 HLTC0I DEG F 2 HL HOT LEG 2 FTC FLUID TEMP +8.10

Table 2.1 Instrumentation used in Composite GERDA Test 1605AA, Continued

D.OATEMWORD61ceEABOSWC-M0ao - AM-D.1Tirr
ABB GBRA 043 970 Blatt I Page A37

ABB Reaktor GmbH

lNo Measurement Unit System Instrument Locationft

151 HLTC02 DEG F 2 HL HOT LEG 2 FTC FLUID TEMP +9.10

152 HLTC03 DEG F 2 HL HOT LEG 2 FTC FLUID TEMP +20.00

153 HLTC04 DEG F 2 HL HOT LEG 2 FTC FLUID TEMP +30.00

154 HLTC05 DEG F 2 HL HOT LEG 2 FTC FLUID TEMP +40.00

155 HLTC06 DEG F 2 HL HOT LEG 2 FTC FLUID TEMP +50.00

156 HLTC07 DEG F 2 HL HOT LEG 2 FTC FLUID TEMP +50.00

157 HLTC08 DEG F 2 HL HOT LEG 2 FTC FLUID TEMP +67.40

158 HLTC09 DEG F 3 SGP SG PRIMRY 2 FTC FLUID TEMP +59.90

159 HLDT01 DEG F 2 HL HOT LEG 10 DT INSUL DT +2.80

160 HLDT02 DEG F 2 HL HOT LEG 10 DT INSUL DT +12.80

161 HLDT03 DEG F 2 HL HOT LEG 10 DT INSUL DT +23.80

162 HLDT04 DEGF 2 HL HOT LEG 10 DT INSULDT +34.50

163 HLDT05 DEG F 2 HL HOT LEG 10 DT INSUL DT +46.20

164 HLDT06 DEG F 2 HL HOT LEG 10 DT INSUL DT +57.20

165 HLDT07 DEG F 2 HL HOT LEG 10 DT INSUL. DT +65.90

166 HLDT0_ DEG F 3 SG SG PRIMRY 10 DT INSUL DT +57.20

167 HLDPO1 PSI

168 HLLV01 PSI

169 HLDPO2 PSI

170 HLLVO2 PSI

171 HLDPO3 PSI

172 HCLV-03 PSI

173 SPDP01 PSI

174 SFOR01 LBM/HR

175 SFDPO2 PSI

176 ISFOR02 LBM/HR

177 9 SFDP3 PSI

178 SFOR03 LB__HR 179= SFDP04 PSI

180 ISFOR04 LBM/HR

181 PSPR01 PSIA

162 PSTCO1 DEG F

183 PSTC04 DEG F

184 PSPC05 DEG F

185 PSRT01 DEG F

1865 PSDPO1 PSI

187 PSOR01 ILBWHR

188 PSDPD2 DPS.

189 PSOR04 LBDGFHR

190 PSDP03 PSI

191 PSOR03 LBM/HR

192 lPSDP04 PSI

193 PSOR04 LMIWHR

194 FPRT01 DEG F

195 FPRT02 DEG F

196 FPRT03 DEG F

197 FPTC01 DEG F

198 IGATC01 DEG F 14 GA GAS ADD 2 FTC FLUID TEMP -999.00

199 GATC02 DEG F 14 GA GAS ADD 2 FTC FLUID TEMP +67.40

200 IGATC03 DEG F 14 GA GAS ADD 2 FTC FLUID TEMP +54.501

Table 2.1 Instrumentation used in Composite GERDA Test 1605AA, Continued

OAMTMfWORM1OBEAhO5lWC4C03.O - AM.rCr~ds
A l I ABB Reaktor GmbH

GBRA 043 970 Blatt / Page A38

INo _ Measurement Unit System Instrument Locationft

201 GATC04 DEG F 14 GA GAS ADD 2 FTC FLUID TEMP +1.00

202 GATC05 DEG F 14 GA GAS ADD 2 FTC FLUID TEMP -22.00

203 GAPR01 PSI 14 GA GAS ADD I P PRESSURE -999.00

204 GSTC01 DEGF 15 GA GAS SAMPL 2" FTC FLUIDTEMP +67.50

205 GSTC02 DEG F 15 GA GAS SAMPL 2 FTC FLUID TEMP +59.00

206 GSTC03 DEGF 15 GA GAS SAMPL 2 FTC FLUIDTEMP +53.50

207 GSTC04 DEG F 15 GA GAS SAMPL 2 FTC FLUID TEMP +7.70

208 GSPR01 PSI 15 GA GAS SAMPL I P PRESSURE +67.50

209 GSPR02 PSI 15 GA GAS SAMPL I P PRESSURE +59.00

210 GSPR03 PSI 15 GA GAS SAMPL I P PRESSURE +53.50

211 GSPRO4 PSI 15 GA GAS SAMPL I P PRESSURE +7.70

212 MSTC01 DEG F

213 MSTC02 DEG F

214 MSTC03 DEG F

215 MSRFOI VOLTS

216 MSRF02 VOLTS

217 MSRF03 VOLTS

218 HPAC01 GAL 10 HPI HP INJECT 19 ACC ACCD. FLOW -999.00

219 VIAC0I GAL 11 V1 1-PH VENT 19 ACC ACCD. FLOW -999.00

220 V2AC01 GAL 12 V2 2-PH VENT 19 ACC ACCD. FLOW -999.00

221 V2ACO2 GAL

222 HPTMOI LBM/HR 10 HPI HP INJECT 13 TMF TURB. FLOW -999.00

223 HPTM02 LBM/HR 10 HPI HP INJECT 13 TMF TURB. FLOW -999.00

224 HPTM03 LBM/HR 10 HPI HP INJECT 13 TMF TURB. FLOW -999.00

225 ISFTMOI LBM/HR

226 SFTM02 LBM/HR

227 CLUS01 GPM 4 CL COLD LEG 5 USF U.S.FLOW -999.00

228 DCOR20 LBM/HR 5 DC DOWNCOMER 8 ORF HEADFLOW 1% -999.00

229 RVLSOI OPNICL 7 RW R.V.V.V. 28 LIM UMIT SW +0.60

230 VILS01 OPN/CL 11 VI I-PH VENT 28 UM UMITSW -999.00

231 VILS02 OPN/CL 11 VI 1-PH VENT 28 UM UMITSW -999.00

232 VILS03 OPN/CL 11 VI 1-PH VENT 28 UM UMITSW -999.00

233 V2LS0I OPN/CL 12 V2 2-PH VENT 28 LIM UMIT SW -999.00

234 V2LS03 OPNICL 12 V2 2-PH VENT 28 UM UMITSW -999.00

235 GALSOI OPN/CL 14 GA GAS ADD 28 LIM UMIT SW +67.50

236 GALS02 OPN/CL 14 GA GAS ADD 28 LIM UMIT SW +54.50

237 GALS03 OPN/CL 14 GA GAS ADD 28 LIM UMITSW +1.00

238 GALS04 OPN/CL 14 GA GAS ADD 28 LIM UMIT SW -22.00

239 SSCPOI WTIDRY

240 SSCP02 WT/DRY

241 SSCP03 WYTDRY

242 SSCP04 WT/DRY

243 SSCP05 WITDRY

244 SSCPo6 WT/DRY

245 SSCP07 WT/DRY

246 SSCP08 WT/DRY

247 SSCP09 WTIDRY

248 SSCPIO WTIDRY

249 SSCPI1 WT/DRY

250 ISSCP12 WT/DRY 122 SGS SG SECOND 16 CP CONDCTVTY +29.50

Table 2.1 Instrumentaton used in Composite GERDA Test 1605AA, Continued

&.0ATeAWVI10EA80%FC . ,=.-.AM&.nWs
AIIB GBRA 043 970 Blatt I Page A39

ABB Reaktor GmbH

INo Measurement Unit System Instrument Locationft

251 SSCP13 WT/DRY 22 SGS SG SECOND 16 CP CONDCTV'Y +29.00

252 SSCP14 WI"/DRY 22 SGS SG SECOND 23 RCP REF. C. P. +21.00

253 RVCP01 WV/DRY I RV CORE VESL 16 CP CONDCTVTY -1.40

254 RVCP02 WT/DRY I RV CORE VESL 16 CP CONDCTVTY -2.40

255 RVCP03 WT/DRY I RV CORE VESL 16 CP CONDCTVTY +0.70

256 RVCP04 WT/DRY I RV CORE VESL 16 CP CONDCTVTY +0.60

257 RVCP01 WTIDRY

258 HLCP01 WT/DRY

259 HLCP02 WT/DRY 2 HL HOT LEG 16 CP CONDCTV'Y +15.00

260 HLCP03 WT/DRY 2 HL HOT LEG 16 CP CONDCTVTY +35.00

261 HLCP04 WT/DRY 2 HL HOT LEG 16 CP CONDCTV'Y +37.00

262 HLCP05 WT/DRY 2 HL HOT LEG 16 CP CONDCTVTY +41.00

263 HLCP06 WT/DRY 2 HL HOT LEG 16 CP CONDCTVTY +45.00

264 HLCP07 WT/DRY

265 HLCP08 WT/DRY 2 HL HOT LEG 16 CP CONDCTV1Y +53.00

266 HLCP09 WV/DRY

267 HLCP10 WTIDRY 2 HL HOT LEG 16 CP CONDCTVTY +61.00

268 HLCP11 WT/DRY 2 HL HOT LEG 16 CP CONDCTViY +65.00

269 HLCP12 WT/DRY 2 HL HOT LEG 16 CP CONDCTVTY +67.20

270 HLCP13 WT/DRY

271 HLCP14 WT/DRY 3 SGP SG PRiMRY 16 CP CONDCTVTY +60.90

272 HLCP15 WT/DRY

273 HLCP16 WTIDRY

274 HLCP17 WT/DRY

275 CLUS02 OPNICL 4 CL COLD LEG 29 ETC MISCELLAN -099.00

276 CLOR20 LBM/HR 4 CL COLD LEG 6 ORF HEADFLOW 1%] -999.00

277 CLLV02 PSI

278 DCLV01 PSI

279 SPPR20 PSI 3 SGP SG PRIMRY 30 KPR CORRD.PR +53.10

280 PRPR20 PSI 6 PR PRESURIZR 30 KPR CORRD.PR +40.50

281 RVPR20 PSI I RV CORE VESL 30 KPR CORRD.PR +7.10

282 PSPR20 PSI 23 STM SEC.STEAM 30 KPR CORRD.PR -999.00

283 PRLV20 FT 6 PR PRESURIZR 31 KLV COLLD.LVL +2.50

284 SPLV20 FT 3 SGP SG PRIMRY 31 KLV COLLD.LVL -2.80

285 SSLV20 FT 22 SGS SG SECOND 31 KLV COLLD.LVL 0.00

286 HLLV20 FT 2 HL HOT LEG 31 KLV COLLD.LVL -1.00

287 HLLV21 FT 3 SGP SG PRIMRY 31 KLV COLLD.LVL +53.00

288 RVLV20 FT I RV CORE VESL 31 KLV COLLD.LVL -16.10

289 SSCP20 FT 22 SGS SG SECOND 32 KCP UP.WET.CP 0.00

290 HLCP20 FTI"

291 HLCP21 FT

292 RVCP20 FT

293 PSOR20 LBM/HR 23 STM SEC.STEAM 33 KOR CALC. FLOW -999.00

294 SFOR20 LBM/HR 21 AFWAUX. FEED 2 FTC FLUID TEMP -999.00

295 SFRF01 DEG F 21 AFWAUX. FEED 33 KOR CALC. FLOW -999.00

296 RVRT03 DEG F

297 RVHRO2 DEG F

298 RVRF02 VOLTS

299 RVRT02 DEG F

300 RVLS04 WT/DRY

Table 2.1 Instrumentation used in Composite GERDA Test 1605AA, Continued

0'"T8&Wi0fl6SlUEABWffC4O== - A&&OrWsa
A BB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page A40

iNo Measurement Unit System Instrument Locatlonft

301 RVLS05 OPN/CL

302 RVHR01 VOLTS

303 RVRF01 VOLTS

304 RVRT01 DEG F

305 RVLS02 WT/DRY

306 RVLS03 OPNICL

307 PRHR01 VOLTS

308 PRRF01 VOLTS

309 PRRT01 DEG F

310 PRLS01 WT/DRY

311 PRLS02 OPN/CL

312 HLHR01 VOLTS

313 lHLRF01 VOLTS

314 HLRT02 DEG F

315 HLLS01 WT/DRY

316 HLLS02 OPN/CL

317 VIRF20 LBM/HR 11 VI 1-PHVENT 38 FLO CALC.FLOW -999.00

318 V2RF20 LBM/HR 12 V2 2-PH VENT 38 FLO CALC.FLOW -999.00

319 RVRF20 LBM/HR 7 RW R.V.V.V. 33 KORCALC.FLOW [%] +0.60

320 CLDPO4 PSI

321 CLLV04 PSI

322 CLOR04 LBM/HR

323 RVLS01 OPN/CL

324 RVLS06 OPN/CL

325 PRTC07 DEG F 8 PR PRESURIZR 25 MTC METAL TC +2.60

326 HLTCI0 DEG F 2 HL HOT LEG 25 MTC METAL TC +33.90

327 HLTC11 DEG F 2 HL HOT LEG 25 MTC METAL TC +65.50

328 CLLV20 FT

329 CLLV21 FT

Table 2.1 Instrumentation used in Composite GERDA Test 1605AA, Continued

M.7MW0= 0W-,0&C0 . M-LOr.Trs
A BII ABB Reaktor GmbH GBRA 043 970 Blatt / Page A41

Chronology of Test 1605AA

(Selected Events From Operators Log and Data Legend File)

TIME EVENT

1025 Reduced core power to 97.4 KW (54.1 %); Power Controller to

auto / cascade; Trip forced circulation pump; Close pump

discharge and suction valves; RVVV open manual; Open RV leak

(10 cm2); PR main heaters off; PR guard heaters on.

1027 HPI activated after reaching TSAT; Steam pressure on constant

control 700 psia.

1030 MK' level control activated.

1031 HLUB viewport voided.

1033 PR refilling; PR level 12 %; RV level 83 %; CLDP02 (Cold Leg

orifice differential pressure) in service.

1035 Steam valve chokes; Steam pressure increasing adjust SFCV-03

AFW valve).

1037 Water at HLUB; PR level decreasing 10 %; RV level 62 %; 35' HL

viewport showing many bubbles.

1040 Steam pressure increased then decreased; HLUB voided.

1043 'MK' injection off.

1044 Steam pressure - 672 psia; THOT = 617.7 F; TCOLD - 440 F; Core

power - 62 KW.

1045 RVVV short-cycled once; 35 ft HL viewport vent black from void

mixture; zeroed CLDP02 & DCDP01 (downcomer orifice differential

pressure).

1048 SGS steam pressure - 693 psia; THOT - 611.1 F; TCOLD = 454 F;

RV level - 59 %; PR level - 13 %; TSAT - 612.7 F; RV pressure =

1693 psia; Downcomer Temperature - 586.9 F; Core power - 61 KW;

Downcomer Flow - 915 ibm/hr.

1056 HPV open.

1059 PR level - 25 %; RV level = 43 %; RV pressure - 1767 psia; 35

ft HL viewport is black from void mixture.

1102 RVVV short-cycled; SGS steam pressure increased to 1100 psia;

Steam valve choked; Primary level < secondary level; PR voided.

1104 Water level below 35 ft HL viewport; PR level = 0 %; RV level =

44 %; HPI flow - 0.106 lbm/sec; RV leak - 0.073 lbm/sec.

1110 CLDPO1 (downcomer liquid level differential pressure probe) and

DCDP01 voltage output is changing rapidly over entire range.

Table 3.1 Detailed Sequence of Events of Composite GERDA Test 1605AA

M:TO V IOTMW 1 CEA& .O5 .DOC - NA-D.Trrs
A BR ABB Reaktor GmbH GBRA 043 970 Blatt / Page A42

1111 Downcomer temperature is saturated.

1118 Primary levels are recovering; SGS steam pressure = 583 psia;

THOT = 573.6 F; TCOLD = 316.7 F; Downcomer temperature = 485.1

F; Primary TSAT - 494 F; RV core power = 47 KW.

1120 Observe small and large bubbles at the 35 ft HL viewport; The

small bubbles appear periodic at a frequency of 2 sec.

1122 PR level = 11 %; RV level = 57 %.

1124 RVVV short cycled once.

1127 Primary loop continues to fill; PR level = 14 %; RV level = 60

%; RV pressure = 691 psia; SGS steam pressure - 528 psia; TSAT

- 501.6 F; Downcomer temperature - 450.4 F; Core power = 45.7 F

KW; Water level above the 35 ft HL viewport.

1136 Added 1.47 SCF (standard cubic feet) of N2 to the RV; Gas

addition pressure = 1711 psia; Primary pressure = 736 psia; RV

and Pr (levels) spiked when gas added.

1140 The PR and RV level oscillations have greatly decreased.

1142 The primary loop continues to refill. PR level = 18 %; RV level - 67 %; RV pressure - 806 psia; SGS steam pressure = 471 psia

(controller - 486 psia); TSAT = 519.8 F; Downcomer temperature

= 414.1 F; HPI flowrate = 0.136 lbm/sec; RV leak rate - 0.091

lbm/sec.

1156 PR level = 22 %; RV level - 68 %.

1204 PR level - 23 %; RV level = 68 %; TSAT - 530.9 F; Downcomer

temperature = 402.9; HPI flow rate - 0.128 lbm/sec; RV leak

rate - 0.117 lbm/sec.

1209 Water observed at HLUB viewport; PR level decreasing rapidly;

RV level increasing; Secondary pressure increased 50 - 100

psia.

1210 Water below HLUB viewport.

1213 Water observed at HLUB viewport; PR level decreased from 5 to 0

%; RV pressure decreased to 740 psia.

1225 A third spillover may have occurred as indicated by the PR and

RV level response.

1233 Added 1.50 SCF (standard cubic feet) of N2 to the RV; Gas

addition pressure - 1794.7 psia; Primary pressure - 799 psia;

RV level - 88 %; HL full.

1254 The upper head thermocouple (RVTC08) indicated 10 F subcooled;

The RV level is 21.5 ft (23.1 ft is full); This discrepancy in

elevation is apparently being caused by the last gas addition

which has collected in the upper section of the RV.

1258 RV level - 21.9 ft.

1305 RV level = 22.4 ft.

Table 3.1 Detailed Sequence of Events of Composite GERDA Test 1605AA, Continued

0.TATMW0St08EA8OZC-OO3.CO - AW.r.rdra
A BB ABB Reakior GmbH

GBRA 043 970 Blatt I Page A43

1310

1317

1321

1323

1325

1330

1332

1333

1335

1337

Table 3.1

RV level = 22.7 ft; PR level = 38 %; RVTC08 = 507 F; Primary

TSAT = 533.4 F.

RV level = 23 ft.

SGS steam pressure controller reached 200 psia.

Switched from 2 to 1 HPI pump; PR level - 38 % (decreasing).

PR level = 26 % (decreasing).

PR level - 14 % (decreasing).

PR level - 8 % (decreasing).

PR level = 0 %; Some bubbles observed at 35 ft HL viewport.

PR level = 0 %; RV level - 94 %.

End of test point.

Detailed Sequence of Events of Composite GERDA Test 1605AA, Continued

WMT8OIMWORDV51O8MAh5t4RC3. - AU.r.Ms
I

I 0

-gCD,

C)D

0

0

(D

0

RELAPS. DESIUGN R.LA5/.

MOD3r2 COMPUTATION k0b) 1' . ARC

PARAMETER SURALB1

P Inlet Temperature 602.15 K 602.15 K 602.15 K 601.5 K 601.38 K

R Outlet Temperature 569.94 K 570.15 K 570.12 K 570.7 K 568.87 K

I Pressure SG-Inlet 151 bar 151.00 bar 151.01 bar 151.3 bar* 154.68 bar

M Pressure SG-Outlet 149.36 bar 149.60 bar 149.74 bar --- 153.94 bar

* Mass Flow Rate 9981.12 kg/s 9984 kg/s 9984 kg/s 10552 kg/s 10061 kg/s

Power 1913.9 MW 1893.5 MW 1904.2 MW 1924.3 MW 1918.5 MW

Inlet Temperature 510.04 K 510.05 K 510.01 K 505.0 K 510.63 K

Outlet Temperature 590.64 K 586.25 K 588.84 K 593.6 K 593.26 K

S Temp.- Superheated 32.09 K 27.27 K 30.23 K 34.9 K 34.54 K

E Pressure SG-Inlet 70.68 bar 70.97 bar 70.58 bar -- 70.7 bar

C Pressure SG-Outlet 69.59 bar 69.96 bar 69.58 bar 68.3 bar 69.7 bar

Mass Flow Rate 1013.29 kg/s 1014.0 kg/s 1014.0 kg/s 980.4 kg/s 1010.6 kg/s

Power 1913.8 MW 1893.5 MW 1913.2 MW 1886.5 MW 1911.5 MW

SG-Inventory 14614 kg 16590 kg 16957 kg -- 13561 kg**

• Pressure in Pressurizer

** 15351 kg incl. steam

U.

CD
I

--4

CD:t'

K3

0

G)

0Y)

GI)

-o

;0

P.

MO~2 CMVtA~ON M IlR M AI

P Inlet Temperature 596.75 K 596.75 K 596.75 K 597.2 K 600.35 K

R Outlet Temperature 575.56 K 575.55 K 575.66 K 575.1 K 568.87 K

I Pressure SG-Inlet 150.98 bar 151.00 bar 150.98 bar 150.8 bar *

M Pressure SG-Outlet 149.49 bar 149.60 bar 149.74 bar -

Mass Flow Rate 9863.1 kg/s 9861 kg/s 9861 kg/s 10431 kg/s 9637 kg/s

Power 1233.80 MW 1230.8 MW 1232.1 MW 1359.4 MW -

Inlet Temperature 488.18 K 488.18 K 488.18 K 485.7 K 484.96 K

Outlet Temperature 595.51 K 594.90 K 595.26 K 593.8 K 599.16 K

S Temp.-Superheated 38.25 K 37.51 K 37.92 K 36.5 K 38.99 K

E Pressure SG-Inlet 68.91 bar 68.93 bar 68.85 bar - --

C Pressure SG-Outlet 68.28 bar 68.34 bar 68.28 bar 67.9 bar 71.2 bar

. Mass Flow Rate 613.53 kg/s 613.6 kg/s 613.6 kg/s 636.0 kg/s 646.1 kg/s

Power 1233.79 W 1230.8 MW 1232.1 MW 1281.4 MW 1308.3 MW

SG-Inventory 9061.32 kg 10510 kg 10320 kg - 8567 kg**

• Pressure in Pressurizer

** 10604 kg incl. steam

CS

CD
II

(D0

co

G)

4-o 0

rk)

G)M

P Inlet Temperature 593.55 K 593.55 K 593.57 K 593.7 K 596.38 

K

R Outlet Temperature 578.85 K 578.75 K 578.86 K 579.0 K 580.96 

K

I Pressure SG-Inlet 151.00 bar 151.00 bar 150.95 bar 150.6 bar*

M Pressure SG-Outlet 149.17 bar 149.60 bar 149.74 bar --..

Mass Flow Rate 9812.52 kg/s 9806 kg/s 9806 kg/s 10343 kg/s 9623 kg/s

Power 849.77 MW 852.07 MW 851.66 MW 895.5 MW ---

Inlet Temperature 474.73 K 474.70 K 474.70 K 482.1 K 473.50 

K

Outlet Temperature 593.06 K 593.45 K 592.70 K 591.4 K 596.05 

K

S Temp.- Superheated 34.52 K 36.66 K 36.11 K 34.81 K 35.31 

K

E Pressure SG-Inlet 69.97 bar 68.10 bar 67.87 bar -- --

C Pressure SG-Outlet 69.59 bar 67.73 bar 67.53 bar 67.4 bar 71.8 bar

Mass Flow Rate 412.9 kg/s 412.9 kg/s 412.9 kg/s 439.3 kg/s 457.6 kg/s

Power 849.75 MW 852.07 MW 851.66 MW 852.07 MW 944.1 MW

SG-Inventory 7276.7 kg 7370 kg 7836 kg -- 6238 kg**

• Pressure in Pressurizer

** 8309 kg incl. steam

cuOU

G)

-0
I

--I

to

CD

0

-IP

cj,

CD

CL'

M

CL

G.

-T

II~LA'5 T~SIGN PMEAPN/

PARAME~1M~ ____ ~MI ___

P Inlet Temperature 588.66 K 588.66 K 588.68 K 588.6 K 591.87 K

R Outlet Temperature 583.64 K 583.64 K 583.71 K 583.6 K 586.87 K.

I Pressure SG-Inlet 151.00 bar 151.00 bar 150.87 bar 151.8 bar*

M Pressure SG-Outlet 149.18 bar 149.60 bar 149.73 bar --

Mass Flow Rate 9694.5 kg/s 9697 kg/s 9697 kg/s 10261 kg/s 9509 kg/s

Power 282.79 MW 284.03 MW 283.99 MW 300.7 MW --

Inlet Temperature 473.19 K 473.15 K 473.15 K 482.2 K 473.20 K

Outlet Temperature 588.61 K 588.85 K 588.66 K 585.7 K 591.43 K

S Temp.- Superheated 30.07 K 32.53 K 32.40 K 29.8 K 31.17 K

E Pressure SG-Inlet 69.72 bar 67.38 bar 67.31 bar -- --

C Pressure SG-Outlet 69.59 bar 67.26 bar 67.20 bar 66.8 bar 71.4 bar

Mass Flow Rate 138.08 kg/s 138.1 kg/s 138.1 kg/s 143.8 kg/s 151.7 kg/s

Power 282.79 MW 284.03 MW 283.99 MW 288.57 MW 310.9 MW

SG-Inventory 3843.93 kg 3939 kg 4174 kg -- --

• Pressure in Pressurizer

U

W

G)

Ca

CD

Co

CD

"-4
0II

-I

0~

Clo

G)

A) 0

CD

.. .... 

.

. --. -,., .- .. .. --

OPURTlm. w'- ws J A"s~

YE-L. SAN~

M4o) aG'&*XD1L

.."RDA,

-.-,APS/MD3`2 VALvES

A~C~

AL.U~8

P Inlet Temperature 588.66 K 591.17 K 588.6 K 591.87 

K

R Outlet Temperature 583.64 K 554.85 K ** 583.6 K 586.87 

K

I Pressure SG-Inlet 151.00 bar 146.77 bar 151.8 bar * --

M Pressure SG-Outlet 149.18 bar 148.05 bar ---

Mass Flow Rate 9694.5 kg/s 1411.58 kg/s** 10261 kg/s 9509 kg/s

Power 282.79 MW 283.98 MW 300.7 MW ---

Inlet Temperature 473.19 K 473.15 K 482.2 K 473.20 

K

Outlet Temperature 588.61 K 588.78 K 585.7 K 591.43 

K

S Temp.- Superheated 30.07 K 32.25K 29.8 K 31.17 

K

E Pressure SG-Inlet 69.72 bar 67,37 bar --..

C Pressure SG-Outlet 69.59 bar 67.26 bar 66.8 bar 71.4 bar

Mass Flow Rate 138.08 kg/s 138.10kg/s 143.8 kg/s 151.7 kg/s

Power 282.79 MW 283.99 MW 288.57 MW 310.9 MW

SG-Inventory 3844 kg 3355 kg -- 

-

cu

CD

A)

ý=CO

* Pressure in Pressurizer

** Nat. Circ. Flow
ABB ABB Reaktor Gb

GBRA 043 970 Blatt I Page A49

Event GERDA RELAP 5 MOD 3.2

10 % Leak at RPV Bottom

PRZ empties

LOCA Signal, 'System Pressure < 117 Bar

1. Interruption of Circulation Flow

Total Stall of Primary Flow

BCM starts

Refill starts

BCM ends

HPI Flow > Leak Flow

HLUB filled to Spill over Elevation

RV (Top Head) filled

145 Seconds

210 Seconds

330 Seconds

8 Minutes

> 22 Minutes

35 Minutes

40 Minutes

52 Minutes

84,5 Minutes

105 Minutes

180 Minutes

145 Seconds

280 Seconds

356 Seconds

- 8,5 Minutes

17 Minutes (1. Time) and

> 22 Minutes

- 35 Minutes

- 40 Minutes

- 56 Minutes

93 Minutes

-106,5 Minutes (Hot Leg)

120 Minutes (SG Piping)

> 116 Minutes

(see Ch. 4.5)

Table 4.6 Timing of Major Phenomena, Comparison of RELAP5 and GERDA

AD~A~eW0=1OEABOSMC4O3=C -AM&.cvxrs

A BB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page BO

APPENDIX B

Original Data Plots from GERDA Composite Test 1605AA

RELAP5 MOD 3.2 Input Deck for the GERDA Test 1605AA Post Test Calculation

RELAP5 MOD 3.2 Restart Input Deck

&.WAftW510So6SWRco&CC03 N&

I

I

§

-0

COMPOSITE TEST : RUN 1605AA REV 0 COMPOSITE TEST ; RUN 1605RAR REV 0

p

Ln

as

wA

aa

4000.. INDEX

+RV KP. R

XSTMKPF F

3500.-

4000..

2500.

13.

0 . I0

'LOT I

VTAB

VPR20

SPR20

PL0TA 0

IVTAS =

PSR2

0

0

C2

00

G)

a*zr

0.0 0.0 20,0 30.0 40.0 50.0

GERDA TIME (MIN.). 0,1024. 12. 12-APFR-83

4 0.0 SO.0 100.0 I50.0 200.0 250.0 500.0

GENOA TIME (I4N.). 0-1024.12, 12-APR-83
I

I

I

S

4:-Q

COMPOSITE TEST ; RUN 1605RR REV 0 COMPOSITE TEST ; RUN 1605RR REV 0

-,o

0

0

(D

ca

5.

11-

I! 1. 0-

INOEX

+AyV KL

ZHL KL

XSGPKL

OSSPKL +CL f(L

XOC KL

ZYPS KL YSG!KL

vi

I-

-j

LV :_.-

- 4

PLOT 4

VTAO

V RVLV20

V MLLV20

V SPLV20

V HLLV21

V CLLV20

V CLLV21

V PALV20

V SSLV20

iO,

PLOT 4

VTRB

AVLV20

HLLV20

SPLV20

HLLV21

CLLV20

CLL V21

PRLV20

SSLV20

0

(0

-3

*a.

0

0~

;oUN

on

G)

F1

0*

m

•, 0.

Lri•~ZIii

-13,

o.R, 10.0 20.0 30.0 40.0 s0,

DEROR TIM.E lAIN. 1. 0.-1024. 12, 12-APR-33

0.0 10.0 100.0 ISO.0 200.0 250.0

GERDA TIME IMIN.). 0-1024.12, 12-APR-63

SI00.0
V U' j COMPOSITE TEST ; RUN I505R REV 0 COMPOSITE TEST ; RUN 1605RR REV 0 O 0

,00 90 1 ,0.00 PLOT 9 0 INDEoX VTAS INDEX VTe o

r 21t ROC ORF OCCOP20 zz.8 XLC OR NCOR20 -nC XL ETC -NONE- XC O ETC R -NONE -

0. ea A

-C 0 4O

+ 0

U. E

0.. O- -S. " I• .0. 0. - 0 4 I -O 0

2. I.0O 00 t.L (• .i .0 5.0 I0.O 100 200 200 )0

GESDR TIME (MIN.). 0-1024,12. 12-FIPR-33 GEROR TIME (MIN. I, 0-1024.12. 12-APRI-83
I

I

3

C/)

CT,

23)

Pa

COMPOSITE TEST ; RUN 160SRR REV 0

PLOT IZ

SVYAO

3SFOfl20

PSOA2 P%0fl20a

-NONE-

-NONE-

-NONE1*

a

-j

S..

-J

-J

I.-

a

U2

a

a

2

C

ICOMPOSITE TEST ; RUN 1605RA REV 0

4l.00

INDEX

X-9f' + FEED

233 X STEAM

4XFO-STY

SON/OT + CLASS

2.00-

0.00

-2.00

-4, 00

-6.00.

-6.00-

-10. 00. _________ _________

PLOT 12. C.

VTRO =.

SFOR20 5"

PSOR20 0

-NONE-

-NONE-

-NONEG)

0

-D

CA

C,

G)w

B

0*

Lu

pi lu

cs

OD

T,

0o c 20. c .0 40.0 5o.0

GER•A TIME (MIN. I. 0-i024. I2. i2-RPR-33

0.0 0.0 100.0 iSO.0 200.0 2S0.0

GEROA TIME IMIN.). 0-1024.12. 12-APR-83

300.0
I

I

_0

cj,

=3

COMPOFITE TEST ; RUN 1S05RR REV 0 COMPOSITE TEST ; RUN 1605RR REV 0

,.w. INDEX'

+fVVLIM

RVI Lill

XVI LIP

OVI LI.M

+V2 LIM

3V2 LIM

ZGA LIP YGA LIP

PLT 16

VTA9

RVL020

VILSO) VILS02

VILSOI

V2L301

GAL¶04

GAL503

GALF02

GALSO;

'U,. -

5,.40.

5. ,,0.

INDEX

+fRVVLIM

ZVI LIM

XVI LIM

OVi LIM

+V2 LIM

RV2 LIM ZGA LIe

YGA LIM

PLOT 16

VTAB

RVLS20

VILSOI

VILS02

VILS03

V2LSOI

V2LS03

GALS03 JT'L$O3 C)

uJ

-j

6-

a

2

6~I

-J

z

I

I..'

£

I.

IKNIWM~KNM - U-

~ ~

-4-

'GR LIM

•:r_2r41 s+

tOA NL1GRL 50

I. 00.

0

co

a,

0

m: 04

CA

00

.4w. - - - -

* 60

.40 - - - -

* 20

-. 00.~~ *

GDU,j

w

0

23

G)

Ca)

c"-13

0,~

0. c 10. T 0 . 0-10 40.0 so'

LIEROA TIME (NIN.I. 0-1024 12, 12-APR-11

Cfo. 11 0.0 W0.0 100.0 Iso.0 200.0 2so.0

GERDA TIME (MIN.). 0-1024.12, 12-APR-83

100.0
I

-4

COMPOSITE TEST ; RUN 1605FR REV 0 COMPOSITE TEST ; RUN 1605RR REV 0

PL3T 17

w W_

CD

I NDEX

+ NPI

XRV LEK x tPV

.00 . * NET

-. 00.

-. 50. ______r____

PLOT I? Q

-NONE- . -NONE- -

-NONE-

-NONE- _

G)

rn

V

08

c"

U. U.

1 .O.0 I0a0 20. 1 40.1 Po0

CERUO TIME ( 0IN.'. O-1024,J2. 12-APR-33

0. c SO.0 300.0 ISO.0 200.0 2SO.0 0O.0

GEROR TIME (HIN. ). 0-1024.12, 12-APR-83
I

3I

Co

COMPOqITE TEST ; RUN 160SARA REV 0 COMPOSITE TEST ; RUN I60SRR REV 0

m

0) -

0) iPLOT 19 0

VTAB ='

VaNMOI 5"

-NONE-

-NONE-

:NONE-

-NONE- *

m

79

Cn

ww

;(D

D)

on

QI

a)

Cr

. C0 23 0 le.0 40.e 5.0

SEA0A TIME (MIN.l. 0-1024 12, 12-RPA-33

90.0 0.0 50.0 100.0 Iso.0 200.0 250.0 300.0

GEROA TIME (NIN.). 0-1024.12. 12-APR-83
I

I

*1

"u

C)

o

CD

0=

C=)

COMPozI1E TEST ; RUN IS5RR REV 0 COMPOSITE TEST ; RUN 160SAR REV 0

PL.#" 26

VTA'3

CLT4Oý

fUtTc04

w4

PLOT 26 0

VTAe

"C CLTCO! "

'C CLTC02

'C CLTC03

'C CLTCO5 CLTC0 4

0ch

I.

D

0I

1.1.2 Jle 30.0 40 0 50.0

• EROR TIME (MIN.I. Q-IO4 1.', 12-RPII-3)

40.0 0.0 SO. 100.0 0SO.* 200.0 2so.O

GEROR TIME IMIN. . 0-1024.12, 12-APR-83
COMPOSITE TEST RUN 1605AA REV 0 COMPOSITE TEST ; RUN 160SAR REV 0

goo .J_ __, PLOo ,oo. C- PLOT0o

1"INDEX VTA9 INDEX VTRe to? I +STMSAl -NONE- +SThSAT -NONE- F•" XSGSSAl -NONE- XSGSSRT -NONE. L XPR SA -NONE- .X)R SAT -NONE0 0

. too 0_ $00. 0

U - ,e0. e.

C G)

+0) t . , I -w€ •e '

CL r

4 a i10A o ZO. 30. 0 40. 4 50.0 60I.1. 0 .0 1O,.0 I00.0 ISO.0* 200. 0 "'0.0 M2;. 0

GERDA TIME (MIN.). 0-1024. 12, 12-APR-83 GEP.0R TIME (MIN. I. 0-1024 12, 12-FIPR-83

Ia

"p

a)co
I

-0

0

COMPOSITE TEST : RUN 1605AA REV 0 COMPOSITE TEST ; RUN 1605AR REV 0

I0 LOTiOS"

U.2

0

PLOTIOS 0

VTAB =

K V -NONE- - KV -NONEKV -NONE- -

IV -NONEKV -NONEKY -NONEKV -NONE-

,V -NONE- B

G)

CA

-gQ0

3•0. 0

GwEl

wr

X

0.0

.'.0 0O.a 20.0 30.0 40.0 -0.0

GERDA TIME (MIN.). 0-1024.12. 12-APR-83

8.0 30.0 100.0 0so.0 200.0 230.0

GEROA TItlE IH!N.1. 0-1024.12, 12-APR-83
I

I

*D

cnCo)

cl

-,oCD

COMPOSITE TEST ; RUN 1605AA REV 0 COMPOSITý TEST ;-RUN 1605RA REV 0

600

750I

700.

$50.

550.

CL

0o0.

PLOT 111

VTAD

RVTCO1

RVTC02

RVTC07

RVTC08

RVTCO9

£0.0

*PLOTIII

VtAe 7 RVTCOi

I RVTC02

3 FlVtCo7 8 RVTCO8

6 RVTC09

0

0

CD

cý

(I

as

G)

z

0.0 10.0 20.0 30.0 40.0 90.0

CERDA TIME (MIN.). 0-1024.12. 12-APR-83

0.0 50.0 100.0 IS0.0 200.0 230.0

GEROA TIME (HIN. ). 0=1024.12. 12-APR-83

300.0
I

I m<

is

I3

CD

CL

C)

CA)

50

COMPOSITE TEST ; RUN 1605AA REV 0 COMPOSITE TEST ; RUN 1605RR REV 0

PLOTI 12

C

Ia-.

IU

a

z

0

U

-I

w

w

0

U

PLOTI12 0

VYAB ~ RVCPOI

RVCP04 a RVCP03 0

0

LA.

(ID

n)

G)

3.1

2,

-0

48

(D

0.0 10.0 20.0 30.0 40.0 10.0

GERDA TIME (MIN.). 0-1024.12. 12-APR-83

60.0 0.0 S0.0 100.0 SO.0 200.0 210.0 lo00.0

GEADA TIME IMJN.1. 0,1024.12. 12-APR-83
I

§

-u

COMPOSITE TEST ; RUN 1605AA REV 0 COMPOSITE TEST ; RUN 1605RA REV 0

-n

0

co

CD

0)

630 -U,

£15. 80..

INDEX

+ 8.

X 9.1

X 20. (

0 30.C

+ 40.(

x 50. (

Z 60.(

Y 67.,

PLOT121 1oo.e

WTAD

HLTCOI

HLTC02 HLTC03

HLTC04 150,.6 IHLTCO5

HLTCO6 'HLTC07

HLTC08

HLRTO1 00-.0

.-. 6,s.00~ L..

0.

2

w

I-

£50.00.

-j

.5.4 . IPLOT)21 0

VTRB

HLTCO1

HLTC02 2L

HLTC03

HLTC04 0)

HLTCO0 E5

HLTC06

HLTCO7

HLTCO8

HLRTOI

G) 0

CD

.2.

a)

G)

a

c0

i

~- 1 .4

0. sas.00.

'060

595. 30.

590. 00

1 -t

0a

I I I I

10.0 20.0 30.0 40.0 50.0

GERDA TIME (MIN.). 0-1024.12, 12-APR-83

0.0 SO.0 100.0 ISO.0 200.0 2S0.0 300.0

GESDA TIME IfIN.1. 0-1024.12. 12-ARfl-83
I -a

U.

COMPOSITE.TEST ; RUN 1605AA REV 0 U m

5L

IPLOTI 23

VTAB

a4LCP02

HLCP03

HLiCP04

HLCP05

HLCP06

HLCPOB

HLCP 1

HLCP I I

HLCD 12

C

N. Iaaa

z

0

0

-D

0

COMPOSITE TEST ; RUN 1605RR REV 0

8. 00 __________

INOEX

+ I5.0

K X 35.0 3"7.0 a. ,;0 • 1 * 45.0

X 53.0

Z 61.

8.10~Al _y _______ 65.0

.6s.°

-,cc-•i

PLOT123 0

VTAB ant

HLCP02 = MLCP03 ~ HLCP04 ~ HLCPOs to

HLCP06

HLCPO8 -

HLCPI0 5

HLCPI I HLCP 12

G)

0

5n

wr

X

0.0 •0.0 20.0 30.0 40.0 50.0

GERDA TIME (MIN.). 0-1024. 12. 12-APR-83

60.0 0.0 10.0 100.0 150.0 200.0 2s0.0

GEROA TIME (MIN.). 0-1024.12. 12-APR-83

JO0. 0
I

I

a

".

COMPOSITE TEST ; RUN 1605AA REV 0 COMPOSITE TEST : RUN 1605RR REV 0

m

0

rC>

(I,

460

65,)

440.

63).

J

.2:.

PLOT124 P100.2 oo

VTAB

HLTC 0

HLTC: i

PRTC07

I

INoEX

+ 34.

X 65.

X 2. 650. 0.

'Am

ssea. a-

$0 00.

:50. a.

Ml• . ,._

PLOT124 0

YTAB =

5 HLTCIO 5

9HLTCl I

6 PATC07

m

en

I00+ 0

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=

a,

a,

CD

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0

-I

C)

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0*

0.0 10.0 20.0 30.0 40.0 SO..0 60.0

GERDA TIME (MIN.). 0-1024.12. 12-APR-83

0.0 S e.a. .0 150.0 200.0 2S0.0

GEROA TIME (HIN. I. 0-1024.12. 12-ARfF-83
I

3

-0

5,7

COMPOSITE TEST ; RUN 1605AA REV 0 COMPOSITE TEST ; RUN 1605AR REV 0

-,

C2

0€

a.

0b

PLOTI31

VTAB

CLICOt

SPTC05

SPTC03

SPTC02

SPTCO2

4HLTC09

SPRT04

SPRT03

SPRTOI

*0. O

PLOT131

CLTCoI

SPTCOS

SPTCO4

SPICO)

LTrco9

SPTC04

SPAT03

SPRT02

0

=L

0

U

U

wr

mb

oo 00 20.0 30.0 40.0 s0.0

GERDA TIME (MIN.). 0-1024. 12. 12-APR-83

6 0.0 SO.0 300.0 ISO.0 200.0 2s0. e

GEROA TIMlE (MIN.l. 0-1024.12, 12-APR-83

-CO. 0
II CA)

Nl)

G)

S.

CL

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5'

COMPOSITE TEST " RUN 1605AA REV 0 COMPOSITE TEST ; RUN 1605RR REV 0

PLOT 132

VTAB

SPRT04

SPRT03

SORT01

SPRT 02

.000.

INOEX

+ -2.9 6 X -2. 8 it X S3. I S'0 S3.1

PLOTI32

VTA8

SPflTO4

SPAT03

SPA TO)

SPRT02 900..

L..

a

a

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I.

I

0~

4.~

Ice

Coo.

M0.-

100..

0

0

Cll

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0,

0.0 10.0 20.0 30.0 40.0 50.0

GERDA TIME (MIN.). 0-1024.12. 12-APR-83

$0.0 0.0 50.0 300. 350.0 200.0 25O.0

GEROA TIHE (M|N. I. 0.1024. 12. 12-APf83

300.0
OMi

COMPOSITE TEST RUN 1605AA REV 0 COMPOSIT TEST RUN 1BO5RA REV 0 V

0 PLOT 141 PLOT,|, 0 o INDEX VTAB INDEX VTAB

S-4. CLTC0O2 - b + -4.5 CLTC02 6 w

I- CLTC03 -44 K I CLTC032 LD

5500. 00 .±.____T___3_1

S60 O.

0 . IA

Cf - 5253 a-Ge.1mG

0

o -.* 'm + I +

40 . • 100 0

0D 0

L.

73. 40. 50 0-~. A0 t0 SlO 500 15

GERD 12APR83 TIE (ilN.. 0102. 1. ERD TIM EMN.I 0-024.2. 2-AR-8

GERDA TIME (MIN.). 0-1024.12. 12-APR-83 GEAOR TIME IMIN. l. 0-1024.12, 12-APR-83
I

I

I

--l

0

2!

COMPOSITE TEST ; RUN 1605AA REV.0, COMPOSITE TEST ; RUN 1605RR REV 0

PLOTis PLOTIS

VTqB

OCTC02

OctcOI

CLTCO5

CLTC04

OCflTOI

RVTCIL

0.

2

w

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2

0

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I0

0

:3.

m

0

0

CA

ca

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G3

CD

C?

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a , o0.0 20.0 30.0 40.0 s0.0

GEROA TIME (MIN.). 0-1024. 12. 12-APR-83

40. 0 C. so.o0 0oo.e :so.e O00.0 0 5.,0

GE4AOA TIME IIN. 1. 0-1024.12. 12-APR-83

2Cc..
I

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COMPOSITE TEST ; RUN 1605AA REV 0

-.o

PLOT161

VTAB

PRICOl

PRTC02

-NONE440.

ol.

a.30

#k.

w

COMPOSITE TEST ; RUN 160SRR REV 0

INOEX

-40P + 22. 9

K5 K 34.2 XPR SAT

6100.

OF_______., 100. 

PLOT161 0

vTne

PRTCOI 0

PATC02

-NONEm

0

W

0~

=

'U

CD

Dl)

'.3.

0 a 10.0 20.0 .10.0 40.0 50.0

GERDA TIME (MIN.). 0,1024. 12. 12-APR.-63

cc a 0.0 50.0 100.0 150.0 200.0 0so.0 !200.0

GEROA TIME (MIN.). 0-1024.12. 12-RPF-83
ABB GBRA 043 970

ABB Reaktor GmbH

Blatt / Page B21

Original Data Plots from GERDA Composite Test 1605AA

COMPOSITE TEST ; RUN 1605RA REV 0

s$c. a.

INOEX

+ 2.

1 38. ee x 36.8

0 46. 5

PLOT) 63

VTRB

PPT C07

PA TC04

PATCOS

PATC06

-J.

cc

W,

fee.

1150.0

20c0.

a. e SO.@ 100.0 Is0.0 200.0 25C.0

GEROA TIIME (MIN. i. 0.1024. 12. 12-APR-83

300. 0

Plot 163 Pressurizer Metal Temperatures (0 - 300 min)

01DAWW0R10WAMR~a= 0) - M4&WsT
I -U0

COMPOSITE rEST ; RUN 1605AA REV0.. COMPOSITE TEST : RUN I6051: REV 0

PLOTI71 ....

CD

5.

toL~3

0~

2

hi

Ia

-J

5~8.

&

INDEX

1 .6

600.0.

550.0 - _______

SOC. 0.o

rso. 0.

400. .

350.0.

NCC. 0 e, I _ _.... ' 

PLOTI7I C

VTAB =

RVTCO9 =

RVTCIO

0

0

Bn

U)

G)

a

a,

-o

8 0 ;0.O 28.8 30.0 40,0 50.8

GERDA TIME (MIN.). 0-1024.12. 12-APR-83

0.0 50.0 100.0 50.0 200.0 250.0 300. 0

GEROR TUlmE IOIN. I, 0-1024. 12. 12-APR-83
I

I

-u

0

-o

C

0

(D

H

5.

0

H

5.

COMPOSITE TEST ; RUN 1605AA REV 0 COMPOSITE TEST ; RUN 1605AR REV 0

PLOT172

VTAB

RVDP0O3

I"NOEX

35-+ .e

PLOTI 72

VTAO

RVOP03

. i5.

l

aI'.

I..

(n 0. 00u

0

oa

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m

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I

G)

G)a)

R=

-A. s

.I •ll

8e •11

0.0 10.6. 20.0 30.0 40.0 50.0

GERDA TIME (MIN.). 0-1024. 12, 12-APR-83

I Ii I " 

0.0 S,.o O0.0O ISO.0 200.0 250.0

GERO TINE If!N. I. 0=1024.12, 12-RPR-83

ICC. C
IoI

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COMPOSITE TEST ; RUN 1605AA REV 0 COMPOSITE TEST ; RUN 1605RR REV 0

Cn

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cl,

0

8

0.

53

-4

P.O'r191 SIJUC.., I. r

see. 1

ir~

a5

+ 1.5 x 4.9

X 8.1

+ 14.1

X 17.,3

Z 20.1

Y 23.1

PLOT) 91

V TAB

SSTCOI

SSTC02

SSTC03

SSTC04

SSTCOS

SSTCO6

SSTCO7

SSYCOO

S5TClO

-NONE -

0.

_j

7J

0.

u

355M TtI

100.

Zoe.___________

0

(0

0

0

=

=

0l

1 3 J0.1, 0.0 30.0 40 . 50.0

GERDA TIME (MIN.). 0-1024. 12. 12-APR-83

g0..) 0.0 50.0 I 00.0 1110.0 I 200.0 2S0.C I

GEROA TIME (MJN.). 0-1024.12, 12-RPP-83

soc. e
I

K

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co

COMPOSITE TEST ; RUN 1605AA REV 0 COMPOSITE TEST ; RUN 650SAR REV 0

0

o

Cc'Co

0

5"

a)

PLOTI 2

.5,)

z

o S3

PLOTI92 0

SSTC2 09

SSTC12

SSTCI3

SSTC16

SSTCI1

SSTCl8

SSTCI e

SSTC20

-NONE-- :

0

0

0

a

79

caU.

Q,

23

cr

a 10.0 20.0 .0.0 40.0 50.0

GERDA TIME (MIN.). 0-1024. 12. 12-APR-83

e.0 so.0 200.0 Is0.0 700.0 250.0 30-. e

GEADA TIME (MIN. ). 0-1024. 12. 12-FIPR-83
I

I

ClD

CD

COMPOSITE TEST ; RUN 1605AA REV. 0. COMPOSITE TEST ; RUN 160SRP REV 0

7S0.

INDEX

+ 1.

X 44.2

0 47.0C

+~ 47.

X( 49. E

ZSTMSA1I

PLOT193

VT AS

SSTC 12

SSTC22

SSTC21

SSTC24

SSTC23

SSTC25

-NONE-

• IA/k A

700'0.

I0 00.0.

-e I- ¢ O

z

o 1

4- 4

$50. e.

550.0

55C. 0..

&-,.A.

INDEX / + 41.2

x 44.2

X X'6 44.2

0 47.0

Y + 47.0

qyl X 49.8

ZsTrsA1

PLOT1 93

VTR13

SSTC19

SSTC22

SSTC21

SSTC24

SSTC23

!ISTC2S

-NONE -

I -

b

0

'a

9L

0

a)

G)

0

0) ,'IV I

A-. 

A ~.2 K-~ 4 320 0 -__________ __________

G),

a)

;04

4S0.0-

II. I I - -- I

0.1 $0.0 20.0 30.0 40.0 ,0.0 a 0W. 0.0

• i I

0.0e s00.0 Iso.0 200.0 2so.0

GEROR TIME IMIN.i. 0-1024.12. 12-APR-83

0e,. e

GERDA TIME (MIN.). 0-1024. 12. I2-APR-83
ABB GBRA 043 970 Blatt I Page B27

ABB Reaktor GmbH

RELAP5 MOD 3.2 Input Deck for the GERDA Test 1605AA Post Test Calculation

* relap5 I mod3.2

* analysendeck: abx.inp

* datum :23.04.98

* analysendeck: abgeleitet von gdr53bwk.inp

* Leck 100%

* VV-Hoehe

* DE-Level 9 m

* RJ 100%

* HP 100%

* VV-Flhche 2.59 cmA2 und K - 1.45

* K-Faktor (FP909) = 0.0

* skalierungsfaktor bezogen auf die gesamtanlage:

* s = 2 x de-rohre(kmk) / de-rohre(gerda)

* 2 x 16013 / 19 = 1686

* mit diesem faktor werden skaliert:

* die nachzerfallsleistung und die einspeise- und ab-

* blasemassenstr~me

= title

100 new transnt

101 run

* -------------------------- 101

* ------------- 102

* -------------------------- 103

104 ncmpress

105 5.0 6.0

110 air

201 150.0 1.0-8 0.25 7

202 600.0 1.0-8 0.25 7

203 3000.0 1.0-8 0.25 7

204 12000.0 1.0-8 0.25 7

inp-chk

si british

0 *restart nummer

20

2

10

20

80

800

800

800

600

4000

4000

4000

" -- -- ==== -- = =-= trips----

" trip f~Ir ende der station~ren rechnung

501 time 0 ge timeof 538 145.0 1 * Zeit aus Versuch 1605AA

*---------------------------------------------------------------------------------------------------

502 time 0 gt null 0 145.0 1

513 time 0 gt null 0 1.+6 1 *immer falsch

* ---- ffnen der heissen entltftungen, loop 1 und 2

504 time 0 gt timeof 501 1855.0 1 * loop 1

505 p 440010000 gt null

506 p 440010000 it null

509 time 0 ge timeof

510 time 0 ge timeof

511 time 0 ge timeof

512 time 0 ge timeof

0

0

82.0+5 n

79.5+5 n

505 0.8 n

509 0.2 n

506 0.8 n

511 0.2 n

DVATRWORIMEASWC-MAX- A%$&iV~s
ABB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page B28

*---- oeffnungs- und schliessdruecke f. 48 u. 79 bar-ventile-----------

524

525

P

P

440010000 gt null 0 48.0+5

440010000 it null 0 47.4+5

440010000 gt null 0 79.0+5

440010000 it null 0 78.4+5

n *oeffnen 48 bar-ventil de ii

" *schliessen 48 bar-ventil de ii

n *oeffnen 79 bar-ventil de i

n *schliessen 79 bar-ventil de i

526 p

527 p

550

551

593

594

514

515

516

517

552

553

546

547

528

529

time

time

time

time

time

time

time

time

0

0

0

0

0

0

0

0

ge

ge

ge

ge

ge

ge

ge

ge

timeof

timeof

timeof

timeof

timeof

timeof

timeof

timeof

689

550

525

593

688

514

527

516

3.00

3.00

3.00

3.00

3.00

3.00

3.00

3.00

n

n

n

n

n

n

n

n

*oeffnungstotzeit 48 bar-vent. de ii

*oeffnungsstellzeit 48 bar-vent. de ii

*schliesstotzeit 48 bar-vent. de ii

*schliesstellzeit 48 bar-vent. de ii

*oeffnungstotzeit 79 bar-vent. de i

*oeffnungsstellzeit 79 bar-vent. de i

*schliesstotzeit 79 bar-vent. de i

*schliesstellzeit 79 bar-vent. de i

cntrlvar

cntrlvar

time 0

time 0

time 0

time 0

290 gt null

290 it null

ge timeof 698

ge timeof 546

ge timeof 553

ge timeof 528

0

0

0.0 n

0.0 n

3.0 n

3.0 n

3.0 n

3.0 n

*7ffnungstotzeit abfahren del

*"Iffnungsstellzeit abfahren del

*schliehtotzeit abfahren del

*schlie~totzeit abfahren del

* --------- 'immer wahr'-trip--------------------------

538 time 0 it null 0 1.0+6 1 * trip, der immer 'wahr' ist

*----------------------------------------------

*--- oeffnen + schliessen anhand kollabierter wasserstaende

* im dampferzeuger fuer rj und rx

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

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

540 cntrlvar

541 cntrlvar

542 cntrlvar

543 cntrlvar

216 it null

216 gt null

216 it null

216 gt null

0

0

0

0

8.4

9.0

8.4

9.0

n *oeffnen rj-einsp. de ,lOt

n *schliessen rj-einsp. de ,12t

n *oeffnen rj-einsp. de , 8t

n *schliessen rj-eins. de ,lOt

548 time 0 gt timeof 501 1655.0 1 *zeitverz"gerung abfahren mit 28 k/h

*580 cntrlvar 70 gt null 0

station,,r

*581 cntrlvar 70 It null 0

580 cntrlvar 70 gt null 0

581 cntrlvar 70 it null 0

576 time 0 ge timeof 580

577 time 0 ge timeof 576

578 time 0 ge timeof 581

579 time 0 ge timeof 578

10000000.0 n * "ffnen vent valves,

0.0

34.3

-34.3

2.0

2.0

2.0

2.0

n

n

n

n

n

n

n

* schlie~en vent valves, station,,r

* "ffnen vent valves, aus 1605aa

* schlie~en vent valves, 1605aa

* "ffnungstotzeit vent valves

* "ffnungsstellzeit vent valves

* schliehstellzeit vent valves

* schliehtotzeit vent valves

-------------- reaktorschutz-trips -----------------

582 p

kuvest

585 time

*585 tit

591 time

*591 time

140010000 it null 0 117.00+5 1 *hkm-druck hot leg 1 sehr tief->

0 gt timeof 592 0.0 1 *13.15 s zeitverz. tj ( notstromfall

.e 0 gt timeof 592 13.15 1 *13.15 s zeitverz. tj ( notstromfall

0 gt timeof 501 0.0 1 *0.9 s zeitverzoegerung sekst

0 gt timeof 501 0.9 1 *0.9 s zeitverzoegerung sekst

D.TATE1JWOMCA3LW8o~C-0C&= - AM&N.1s
ABB ABB Reaktor GmbH

GBRA 043 970 Blati I Page B29

592 time 0 gt timeof 582 0.0

*592 time 0 gt timeof 582 0.9

*****593 time 0 gt timeof 663

*****594 time 0 gt timeof 664

1 *0.9 s zeitverzoegerung kuvest

1 *0.9 s zeitverzoegerung kuvest

120.9 1 *120.9 s zeitverzoegerung noss loop

120.9 1 *120.9 s zeitverzoegerung noss lopp

1

2

596 time 0 gt timeof 591 0.0 1 *5.5 s zeitverzoegerung start rj-red. i

*596 time 0 gt timeof 591 16.5 1 *5.5 s zeitverzoegerung start rj-red.

597 time 0 gt timeof 592 16.5 1 *13.5 s zeitverzoegerung start rj-red.ii

*597 time 0 gt timeof 592 24.5 1 * 24.5 s - - bei notstromfall

598 time 0 gt timeof 592 0.0 1 *zeitverz. freischalt. 48 bar-v.

*598 time 0 gt timeof 592 36.5 1 *zeitverz. freischalt. 48 bar-v.

* bei erreichen von kuvest (trip 598 wird true)

* tripkarten 540 bis 543 austauschen (rj-regelung

* von 10/12t auf 28/30t setzen)

599 time 0 gt timeof 591 0.0 1 *zeitverz. freischalt. 79 bar-v. bei

notstrom

*599 time 0 gt timeof 591 26.5 1 *zeitverz. freischalt. 79 bar-v. bei

notstrom

*599 time 0 gt timeof 591 10.0 1 *zeitverz. freischalt. 79 bar-v.

i

*

*

*

m•It•llmm•m•sJ•sJ•Im• logische trips

648 576 and -577

649 578 and -579

n * "ffnungstrip vent valves

n * schliehtrip vent valves

------------------------ regelung rj-----------------------------------

* regelung rj-einspeisung in de i

670 -672 and 540 n *grenzwerte 540 und 541 ohne verzoegerungen

671 672 and -541 n

672 670 or 671 n *schaltung rj-red. de i

673 672 and 596 n *schaltung nur, wenn sekst oder kuvest ausgeloest

* regelung rj-einspeisung in de ii

674 -676 and 542 n *grenzwerte 542 und 543 ohne verzoegerungen

675 676 and -543 n

676 674 or 675 n *schaltung rj-red. de ii

677 676 and 597 n *schaltung nur, wenn sekst oder kuvest ausgeloest

678 -673 and 538 n *komplement zu 673

679 -677 and 538 n *komplement zu 677

680

681

682

683

688

689

514

516

550

593

526

524

and

and

and

and

and

and

-515

-517

-551

-594

599

598

n

n

n

n

n

n

n

n

*

*

*

*

*

*

oeffnen 79

schliessen

oeffnen 48

schliessen

oeffnen 79

oeffnen 48

bar ventil de

79 bar ventil

bar ventil de

48 bar ventil

bar ventil de

bar ventil de

i

de i

ii

de ii

i nach kuvest

ii nach kuvest

690 546 and -547

691 528 and -529

698 552 and 548

*

*

*

I'ffnen abfahren del

schliessen abfahren del

I'ffnen abfahrstrang del nach 1800 s

DiU1MWcOi5106EASCS4RC-=oDoC -. ADrT
ABB GBRA 043 970 Blatt / Page B30

ABB Reaktor GmbH

694 509 and -510

695 511 and -512

n

n

*

*

*

*

eingabe der komponenten

* ... eingabe reaktordruckbehalter

* komponente 102

1020000 vsslbtm branch

1020001 1 1

1020101 0.00345117 0.2

1020200 3 1.53295+07

1021101 102010000 10000l

1021201 1.0967 0.0

0. 0. 90.0

571.760

)000 0.001446

0.0

0.2 2.0-5 0.0 0000000

0.0 0.0 0001000

* komponente 905

* break valve

9050000 break valve

* f - 0.001 m^2 (10 cmA2)

* f-gerda - 0.001/1686 - 0.0000005931 mA2

*9050101 102000000 906000000 0.0000005338 0.0 0.0 0000100

1.0

9050101 102000000 906000000 0.0000005931 0.0 0.0 0000100

1.0

9050201 1 0. 0. 0.

9050300 mtrvlv

9050301 501 513 66.67 0. 0

1.0 1.0

1.0 1.0

9060000 tha tmdpvol

9060101 100.0 0.0 400.0 0. 0.

9060200 4

9060201 0. 1.+5 293.00

9060202 1.+6 1.+5 293.00

0. 0. 0. 0000011

1.

1.

* komponente 100

* unteres plenum rdg

1000000 unt.ple pipe

1000001 2

1000101 0.00345117 1

1000301 1.92 1

1000601 90.0

1000801 2.0-5 0

1000901 0.0 0.0

1001001 0000000

1001101 0001000

1001201 3 1.53219+07

1001202 3 1.53120+07

1001300 1

1001301 1.0967 0.0

7.267504-4

0.375

2

2

2

2

1

2

1

571.758 0.0 0.0 0.0 1

571.754 0.0 0.0 0.0 2

0 1

* komponente 105

* verbindung zw untplm und core

1050000 untplm sngljun

1050101 100010000 110000000 0.0136361 0. 0. 0001000 1.0 1.0 1.0

OCAMTENOFlM1OMAWNAhO. MC -AM&.~Tda
ABB ABB Reaktor GmbH

GBRA 043 970 Blatt / Page B31

1050201 1 1.0967

* komponente 110

* rdg / core

1100000 core pipe

1100001 6

1100101 0.0136361 4

1100301 0.4875 4

1100601 90.0

1100801 2.0-5 0

1100901 0. 0.

1101001 0000000

1101101 0001000

1101201 3 1.53103+C

1101202 3 1.53069+C

1101203 3 1.53036+C

1101204 3 1.53003+C

1101205 3 1.52949+C

1101206 3 1.52876+C

1101300 1

1101301 1.0967

0. 0.

0.0059892 6

1.091 6

6

6

5

6

5

17 576.589

17 581.345

17 585.917

17 590.459

)7 590.461

)7 590.458

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

1

2

3

4

5

6

0.0 0 5

* komponente 120

* rdg hoehe auslaufstutzen

1200000 coreaus branch

1200001 3 1

1200101 0.0059892 0.2 0 0 90.0 0.2

1200200 3 1.52832+07 590.456

1201101 110010000 120000000 0.007495

1202101 120010000 270000000 0.007495

1203101 120010000 130000000 0.0017466

1201201 1.0967 0. 0.

1202201 0. 0. 0.

1203201 1.0967 0. 0.

2.0-5 0 0000000

0.

0.

4.296

0.

0.

5.36

0001000

0001000

0001000

* komponente 270

* rdg oberes plenum unterer teil

2700000 rdgobpl branch

2700001 0 1

2700101 0.0059892 1.470 0. 0. 90. 1.470 1.6-6 0

2700200 3 1.52776+07 590.818

0000000

* komponente 265

* ueberstroemvorrichtungen

2650000 vv valve

* f = 0.7948 m^2

* f-gerda - 0.7948/1686 - 0.0004714 mA2

* K-Wert wurde aus Versuch 1605AA abgeleitet

2650101 270010000 260010000 0.000259 1.45 1.0+9

2650201 1 0. 0. 0.

2650300 mtrvlv

2650301 648 649 0.5 0 0

0000100 1.0 1.0 1.0

* komponente 275

* verbindung zw ob plm 1+2 teil

2750000 obplm sngljun

2750101 270010000 280000000 0.0059892 0. 0. 0001000 1.0 1.0 1.0

2750201 1 0.0 0. 0.

0,.A 1NW •IOEMSNRC-=W.DC - AM-&.Tgs
Pi gu ABB Reaktor GmbH

GBRA 043 970 Blatt I Page B32

* komponente 280

* rdg ob plm,ob teil

2800000 rdgobplm snglvol

2800101 0.0059892 1.6345 0 0

2800200 3 1.52672+07 590.818

* ..... eingabe heisser strang

90. 1.6345 1.6-6 0. 0000000

* komponente 130

* hot leg : rdg bis vor oberem kruemme2

1300000 hotlel snglvol

1300101 0.003599 2.480 0 0 90.0 2.480

1300200 3 1.52729+07 590.451

r 1.teil loop i

2.0-5 0.0 0000000

* komponente 131

* verbindung: 130 und 132

1310000 hotverb sngljun

1310101 130010000 132000000 0.003599 0.255 0.255 0001000 1.0

1310201 1 1.0967 0. 0.

1.0 1.0

* komponente 132

* hot leg : 2. teil

1320000 hotlel pipe

1320001 16

1320101 0.003599

1320301 0.9746885

1320601 90.0

1320801 2.0-5 0.0

1320901 0.0 0.0

1321001 0000000

1321101 0001000

mit abzweig zum druckhalter loop i

1321201

1321202

1321203

1321204

1321205

1321206

1321207

1321208

1321209

1321210

1321211

1321212

1321213

1321214

1321215

1321216

1321300

1321301

3

3

3

3

3

3

3

3

3

3

3

3

3

3

3

3

1

1.52612+07

1.52546+07

1.52481+07

1.52415+07

1.52349+07

1.52283+07

1.52218+07

1.52152+07

1.52086+07

1.52020+07

1.51954+07

1.51889+07

1.51823+07

1.51757+07

1.51691+07

1.51626+07

16

16

16

16

15

16

15

590.447

590.443

590.440

590.437

590.434

590.430

590.427

590.424

590.421

590.417

590.414

590.411

590.408

590.404

590.401

590.398

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

1.0967 0 0 15

* komponente 135

* verbindung: hot leg und druckhalter

1350000 pressjun sngljun

1350101 310000000 132000000 0.000172 144.89 144.89 0001000 1.0 1.0 1.0

1350201 1 0.0 0.0 0.

M.M* MMMW~aD M.~
ABB ABB e0 GmbH GBRA 043 970 Blatt / Page B33

* komponente 140

* oberer kruemmer bis zum hoechsten punkt loop i

1400000 hipoint branch

1400001 1 1

1400101 0.003523 3.271 0 0 90.0 3.271 2.0-5 0.0 0000000

1400200 3 1.51482+07 590.391

1401101 132010000 140000000 0.003599 0.255 0.255 0001000

1401201 1.0967 0. 0.

*

*

*

*

*

*

komponente 921

heisse entldftungsleitung (loop 1)

flachenanpassung aus gbra 027402, 21.12.93, kohler

flachenanpassung fachbesprechnungsbericht k-648 vom 17.08.81

begutachtung des ya- und yp-systems (g-5829)

9210000 vv valve

* f - 0.0002 m^2 (2 yen

* f-gerda = 0.0002/1686

* Durchmesser-Gerda = 0

* Gerda-Magnetband: 3 c

*9210101 140010000 920000000

1.0

*9210101 140010000 920000000

1.0

9210101 140010000 920000000

1.0

9210201 1 0. 0. 0.

9210300 mtrvlv

9210301 504 513 0.5 0 0

tile)

= 0.0000001186

,05 cm

m^2

0.000000177 9 0.0 1.+9 0000100 1.0 1.0

0.0000001963 0.0 1.+9 0000100 1.(

0.0000001186 0.0 1.+9 0000100 1.0

) 1.0

1.0

* komponente 920 containment

9200000 contain tmdpvol

9200101 1.+6 1.+6 0. 0. 0. 0. 0. 0. 11

9200200 4

9200201

9200202

time

0.

1.+6

press

1.+5

1.+5

temp

293.

293.

1.

1.

* komponente 145

* vebindung : kruemmerteile am hoechsten punkt hot

1450000 bogen sngljun

1450101 140010000 150000000 0.003599 0.255 0.255

1450201 1 1.0967 0. 0.

leg loop i

0001000 1.0 1.0 1.0

* komponente 150

* oberer kruemmer : hoechster punkt bis einlass de loop i

1500000 inlsgl snglvol

1500101 0.003761 4.691 0 0 -90.0 -4.691 2.0-5 0.0 0000000

1500200 3 1.51529+07 590.395

* komponente 155

* verbindung : hot leg -> einlass de loop i

1550000 hlinsgl sngljun

1550101 150010000 170000000 0.0029655 0.99 1.139 0001000 1.0 1.0

1550201 1 1.0967 0. 0.

* .... eingabe primaerteil dampferzeuger ....

* --- komponenten des primaerstranges----------------

1.0

z

D.TATENWORNI5OSEA8O9NRC43DC -. AD
A EB ABB Reakor GmbH GBRA 043 970 Blalt I Page B34

* komponente 170

* heizrohre loop i

1700000 del pipe

1700001 52

1700101 0.002964 52

1700301 0.305386 52

1700601 -90.0 52

1700801 3.2-6 0.014094 52

1700901 0.06 0.06 51

1701001 0000000 52

1701101 0001000 51

1701201 3 1.51695+07 590.404 0.0 0.0 0.0 1

1701202 3 1.51715+07 590.405 0.0 0.0 0.0 2

1701203 3 1.51735+07 590.406 0.0 0.0 0.0 3

1701204 3 1.51755+07 590.407 0.0 0.0 0.0 4

1701205 3 1.51776+07 590.408 0.0 0.0 0.0 5

1701206 3 1.51796+07 590.409 0.0 0.0 0.0 6

1701207 3 1.51816+07 590.410 0.0 0.0 0.0 7

1701208 3 1.51836+07 590.411 0.0 0.0 0.0 8

1701209 3 1.51856+07 590.412 0.0 0.0 0.0 9

1701210 3 1.51876+07 590.413 0.0 0.0 0.0 10

1701211 3 1.51896+07 590.414 0.0 0.0 0.0 11

1701212 3 1.51916+07 590.414 0.0 0.0 0.0 12

1701213 3 1.51936+07 590.415 0.0 0.0 0.0 13

1701214 3 1.51956+07 590.416 0.0 0.0 0.0 14

1701215 3 1.51976+07 590.416 0.0 0.0 0.0 15

1701216 3 1.51996+07 590.417 0.0 0.0 0.0 16

1701217 3 1.52016+07 590.417 0.0 0.0 0.0 17

1701218 3 1.52036+07 590.418 0.0 0.0 0.0 18

1701219 3 1.52056+07 590.418 0.0 0.0 0.0 19

1701220 3 1.52076+07 590.417 0.0 0.0 0.0 20

1701221 3 1.52096+07 590.417 0.0 0.0 0.0 21

1701222 3 1.52116+07 590.416 0.0 0.0 0.0 22

1701223 3 1.52136+07 590.415 0.0 0.0 0.0 23

1701224 3 1.52156+07 590.413 0.0 0.0 0.0 24

1701225 3 1.52176+07 590.411 0.0 0.0 0.0 25

1701226 3 1.52196+07 590.408 0.0 0.0 0.0 26

1701227 3 1.52216+07 590.405 0.0 0.0 0.0 27

1701228 3 1.52237+07 590.401 0.0 0.0 0.0 28

1701229 3 1.52257+07 590.395 0.0 0.0 0.0 29

1701230 3 1.52277+07 590.389 0.0 0.0 0.0 30

1701231 3 1.52297+07 590.381 0.0 0.0 0.0 31

1701232 3 1.52317+07 590.371 0.0 0.0 0.0 32

1701233 3 1.52337+07 590.359 0.0 0.0 0.0 33

1701234 3 1.52357+07 590.345 0.0 0.0 0.0 34

1701235 3 1.52377+07 590.328 0.0 0.0 0.0 35

1701236 3 1.52397+07 590.308 0.0 0.0 0.0 36

1701237 3 1.52417+07 590.283 0.0 0.0 0.0 37

1701238 3 1.52437+07 590.254 0.0 0.0 0.0 38

1701239 3 1.52457+07 590.218 0.0 0.0 0.0 39

1701240 3 1.52477+07 590.175 0.0 0.0 0.0 40

1701241 3 1.52497+07 590.123 0.0 0.0 0.0 41

1701242 3 1.52517+07 590.060 0.0 0.0 0.0 42

1701243 3 1.52537+07 589.985 0.0 0.0 0.0 43

1701244 3 1.52557+07 589.890 0.0 0.0 0.0 44

1701245 3 1.52578+07 589.776 0.0 0.0 0.0 45

1701246 3 1.52598+07 588.518 0.0 0.0 0.0 46

1701247 3 1.52618+07 585.622 0.0 0.0 0.0 47

1701248 3 1.52639+07 583.055 0.0 0.0 0.0 48

1701249 3 1.52659+07 580.881 0.0 0.0 0.0 49

1701250 3 1.52680+07 578.987 0.0 0.0 0.0 50

1701251 3 1.52701+07 577.109 0.0 0.0 0.0 51

DATBVMRZ10EABOMlNR.OO1CO - AIA.WvtTS
A BIP ABB RatrGb

GBRA 043 970 Blatt I Page B35

1701252 3 1.52722+07

1701300 1

1701301 1.0967 0 0 51

571.733 0.0 0.0 0.0 52

* komponente 180

* unteres plm del loop i

1800000 lowplml branch

1800001 2 1

1800101 0.003655 2.169 0. 0. -90. -2.169

1800200 3 1.52810+07 571.737

1801101 170010000 180000000 0.0029654

1802101 180010000 904000000 0.003493

1801201 1.0967 0. 0.

1802201 1.0967 0. 0.

3.2-6 0.0 0000000

0.747

1.183

0.598 0001000

1.183 0001000

* .... eingabe sekundaerteil dampferzeuger

* komponente 420

* sec de loop i

4200000 secdel pipe

4200001 52

4200101 0.004777

4200301 0.305386

4200601 90.0

4200801 3.2-6 0.015622

4200901 2.5 2.5

4201001 0000000

4201101 0001000

4201201 3 7.91540+06

4201202 3 7.91299+06

4201203 1

4201204 1

4201205 1

4201206 1

4201207 1

4201208 3 7.90519+06

4201209 3 7.90506+06

4201210 3 7.90494+06

4201211 3 7.90482+06

4201212 3 7.90470+06

4201213 3 7.90458+06

4201214 3 7.90446+06

4201215 3 7.90434+06

4201216 3 7.90422+06

4201217 3 7.90411+06

4201218 3 7.90399+06

4201219 3 7.90387+06

4201220 3 7.90376+06

4201221 3 7.90364+06

4201222 3 7.90352+06

4201223 3 7.90341+06

4201224 3 7.90329+06

4201225 3 7.90318+06

4201226 3 7.90306+06

4201227 3 7.90295+06

4201228 3 7.90283+06

4201229 3 7.90272+06

4201230 3 7.90260+06

4201231 3 7.90249+06

4201232 3 7.90237+06

4201233 3 7.90226+06

4201234 3 7.90214+06

52

52

52

52

51

52

51

494.050

547.753

566.551

567.316

567.307

567.301

567.288

572.077

574.876

577.226

579.202

580.940

582.454

583.722

584.784

585.676

586.424

587.054

587.583

588.029

588.404

588.720

588.986

589.211

589.400

589.560

589.694

589.807

589.903

589.983

590.054

590.113

590.163

590.204

0.0

0.0

0.00700

0.01876

0. 03337

0.03499

0.61103

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

19

20

21

22

23

24

25

26

27

28

29

30

31

32

33

34

D:•TATIBC•RDMIOB8OS"CMDO - AM-DrTWs
A BB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page B36

4201235 3 7.90203+06

4201236 3 7.90191+06

4201237 3 7.90180+06

4201238 3 7.90168+06

4201239 3 7.90157+06

4201240 3 7.90145+06

4201241 3 7.90134+06

4201242 3 7.90122+06

4201243 3 7.90111+06

4201244 3 7.90099+06

4201245 3 7.90088+06

4201246 3 7.90076+06

4201247 3 7.90065+06

4201248 3 7.90053+06

4201249 3 7.90042+06

4201250 3 7.90030+06

4201251 3 7.90019+06

4201252 3 7.90007+06

4201300 1

4201301 0.0 0.0

4201401 0.020914 0 1.0

590.239

590.267

590.291

590.311

590.327

590.340

590.352

590.361

590.368

590.374

590.379

590.383

590.386

590.388

590.390

590.391

590.392

590.393

0 51

1.0 51

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

35

36

37

38

39

40

41

42

43

44

45

46

47

48

49

50

51

52

*

*

komponete 425

4250000

4250101

4250201

f = 2 x 2.1244 = 4.2488 m]' (2 de)

f-gerda - 4.2488/1686 - 0.002520

dwncrl sngljun

420010000 440000000 0.00252 0.0 0.0

1 0.0 0.0 0

0001000 1.0 1.0 1.0

* komponente 440

4400000 bmsoivl branc

4400001 0

4400101 0.00252 5.0

4400200 3 7.90001+06

0.0 0.0 0.0 0.0 6.-5 0.0

590.393

0000000

* komponente 445

4450000 msoivl valve

4450101 440010000 470000000 0.00252

4450201 1 0. 0.04464 0.

4450300 mtrvlv

4450301 513 502 0.0666 1.0 0

* komponente 470

4700000 turbine tmdpvol

4700101 500.0 500. 0. 0. 0. 0.

4700200 4

4700201 0.0 7.90000+06 520.920

4700202 1.+6 7.90000+06 520.920

1.15 1.15 0001100 1.0 1.0 1.0

0. 0. 0000011

1. 1.

* komponente 480

* temperaturabsenkung 28 k/h

4800000 con48del tmdpvol

4800101 500.0 500. 0. 0. 0. 0. 0. 0.

4800200 1

*time temp x

4800201 0.0 533.81 1.0

4800202 1800.0 533.81 1.0

0000011

DMATEWOFMDWASO C-O .- IA-Th.lWs
A BB ABB Reaktor GmbH

GBRA 043 970 Blatt / Page B37

4800203 22456.0 373.15 1.0

4800204 100000.0 373.15 1.0

* komponente 481

* druckreduzierstation loop i

4810000 con48del valve

* flache: 0.007 m^2 (2 ventile)

* f-gerda = 0.007/1686 - 0.00000415 m^2

4810101 440010000 480000000 0.00000415 0. 1.+9 0001100

4810201 1 0. 0. 0.

4810300 mtrvlv

4810301 690 691 0.3333 0. 0

1.0 1.0 1.0

* komponente 485

* fd-sicherheitsventile (2 ventile) loop i

4850000 fd-si-vl valve

* flaeche angepasst an durchsatz

* flache: 4 x 0.03916 mA2 (4 ventile)

* f-gerda = 4 x 0.03916/1686 = 0.0000929 m^2

4850101 440010000 500000000 0.0000929 0. 0. 0001100

4850201 1 0. 0. 0.

4850300 mtrvlv

4850301 694 695 5.0 0.0 0

1.0 1.0 1.0

* komponente 500

* atmosphaere

5000000 atmos tmdpvol

5000101 1.+6 1.+6 0. 0. 0. 0.

5000200 4

* time press temp

5000201 0.0 1.+5 293.00 1.

5000202 1.+5 1.+5 293.00 1.

0. 0. 0000011

* komponente 505

* 48 bar condenser valves (2) loop i

5050000 con48del valve

* flaeche angepasst an durchsatz

* flAche: 0.007 m^2 (2 ventile)

* f-gerda - 0.007/1686 = 0.00000415 mA2

* Vergleich mit gemessener Gerda-Kurve - Vergr"kerung der

10%

5050101 440010000 520000000

5050201 1 0. 0. 0.

5050300 mtrvlv

5050301 682 683 0.3333 0. 0

FlAche um.

0.00000457 0. 0. 0000100 1.0 1.0 1.0

* komponente 520

* atmosphaere

5200000 atmos

5200101 1.+6 1.+6

5200200 4

* time pri

5200201 0.0 1.

5200202 1.+5 1..

tmdpvol

0. 0. 0. 0. 0. 0. 0000011

ess

+5

+5

temp

293.00 1.

293.00 1.

* komponente 525

* 79 bar condenser valves (2) loop i

5250000 con79del valve

* flaeche angepasst an durchsatz

* flAche: 0.0042 m^2 (2 ventile)

* f-gerda = 0.0042/1686 = 0.00000249 m^2

5250101 440010000 540000000 0.00000349 0. 0. 0000100 1.0 1.0 1.0

*5250101 440010000 540000000 0.00000249 0. 0. 0000100 1.0 1.0 1.0

OTAwMwORMIC6E~M9JUc.M - AMOM.VS
ABB GBRA 043 970 Blatt / Page B38

ABB Reaktor GmbH

5250201

5250300

5250301

1 0. 0. 0.

mtrvlv

680 681 0.3333

* komponente 540

* atmosphaere

5400000 atmos tmdpvol

5400101 1.+6 1.+6 0.

5400200 4

* time press

5400201 0.0 1.+5

5400202 1.+5 1.+5

0. 0

0. 0. 0. 0. 0. 0000011

:emp

293.00

293.00

1.

1.

*

*

* hauptspeisewasserversorgung

*

*

* komponente 400

* einlauf

4000000 einlaufl tmdpv

4000101 100.0 0. 400.

4000200 3

* time press

4000201 0.0 7.928+6

4000202 1.+6 7.928+6

40500

40501

40502

40502

40502

40502

40502

40502

40502

40502

40502

A1

0 0 0 0 0 0000011

temp

321.93

321.93

(2 de)

L686 = 0.0000866 m^2

)000 0.0000866

0 0

0 0

komponente 405

verbindung

flhche: 0.146 m^,

f-gerda - 0.146/1

•00 hspwl tmdpjun

.01 400000000 41400(

00

201

202

;03

204

;05

206

207

:08

1

0.0

5.0

10.0

20.0

30.0

145.0

160.0

1.+6

0.0

0.0230

0.0375

0.0425

0.0441

0.0441

0.0

0.0

0

0

0

0

0

0

0

0

0

0

0 0

* komponente 414

* speisewasserringraum

4140000 down1 snglvol

4140101 0.0000866 1.0

4140200 3 7.91713+6

rl-einspeisung loop i

0. 0. 0. 0.0

321.93

3.2-6 0.0 0000000

* komponente 410

* downcomer rj/rx-einpeisung loop i

4100000 rjrxdcrl branch

4100001 2 1

4100101 0.0000866 1.0 0. 0. 0. 0.0

4100200 3 7.91673+6 321.93

4101101 410010000 420000000 0.0000866

4102101 414010000 410000000 0.0000866

4101201 0.0 0. 0.

4102201 0.0 0. 0.

3.2-6 0.0 0000000

0.0 1.+9 0001000

0.0 1.+9 0001000

*

D1fmATEMhNOBERC-COM=O - AM&O.WS
ABII ABB RatrGb GBRA 043 970 Blatt I Page B39

*------ notspeisewasserversorgung----------------------------------

* komponente 620

* rj-vorlagebehaelter (1 behaelter) loop i

6200000 rj-tank2 tmdpvol

6200101 100.0 0. 400. 0. 0. 0. 0. 0. 0000011

6200200 3

* time press temp

6200201 0.0 1.00+5 321.93

6200202 1.+5 1.00+5 321.93

* komponente.624

* rj - einspeiseventil loop i

6240000 rjvent2 valve

* flaeche angepasst an durchsatz

* flache: 2 x 0.00785 m^2 (2 ventile)

* f-gerda - 2 x 0.007850/1686 - 0.00000931 m^2

6240101 620000000 628000000 0.00000931 0.0 0.0

6240201 1 0.0 0.0 0.0

0001100 1.0 1.0 1.0

6240300

6240301

*6240301

mtrvlv

673

677

678 0.1818 0.0 * 0.03333

679 0.1818 0.0 * 0.03333

* komponente 628

* rj - einspeiseleitung loop i

6280000 rj-ltg2 snglvol

* flaeche angepasst an durchsatz

6280101 0.00000931 2.0 0. 0. 0. 0. 0. 0.1 00

6280200 3 1.0+5 321.93

* komponente 632

* notspeisewassereinspeisung (1 rj-pumpe) loop i

6320000 notspw2 tmdpjun

* flaeche angepasst an durchsatz

6320101 628010000 410000000 0.00000931

6320200 1 538 cntrlvar 225

6320201 0. 0. 0. 0.

6320202 300. 300. 0. 0.

* ..... eingabe kalte straenge bis hkmp ...............

* komponente 904

9040000 coldleg branch

9040001 0 1

9040101 0.006184 0.467 0. 0. 90.0 0.467 2.0-5 0.0 0000000

9040200 3 1.52870+07 571.74

* komponente 907

* verbindung komp 904 und 200

9070000 coldleg tmdpjun

9070101 904010000 200000000 0.002752

9070200 1

9070201 0.0 1.0967 0. 0

9070202 145.0 1.0967 0. 0

D.ATBEWOA•1OBSEA •O•C.403DOC - AM-M.ITs
A BB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page B40

9070203 150.0

9070204 100000.

0.0

0.0

0. 0

0. 0

*9070000

*9070101

*9070201

coldleg sngljun

904010000 200000000 0.003599 0.02033 0.03367 0001000 1.0 1.0 1.0

1 1.0918 0. 0

* komponente 908

9080000 coldleg valve

9080101 904010000 200000000 0.002752

9080201 1 0. 0. 0.

9080300 mtrvlv

9080301 501 513 66.67 0. 0

0.0 0.0 0001100 1.0 1.0 1.0

* komponente 200

* cold leg bis hkmp loop i

2000000 coldleg branch

2000001 0 1

2000101 0.002752 2.408 0

2000200 3 1.52801+07 571

0 90.0 2.408 2.0-5 0.0 0000000

.738

* komponente 909

* verbindung komp 200 und 290

9090000 coldleg sngljun

9090101 200010000 220000000 0.002752 0.0

1.0

*9090101 200010000 220000000 0.002752 200.0

1.0

9090201 1 1.0967 0. 0

0.0

0.0

0001000 1.0 1.0

0001000 1.0 1.0

* .-.-- druckseitige kalte straeAnge

* komponente 220

* auslass hkp bis einlass downcomer loop i

2200000 cld branch

2200001 0 1

2200101 0.00349314 1.383 0 0 -64.27 -1.246

2200200 3 1.52759+07 571.737

2.0-5 0.0 0000000

* komponente 230

* druckleitung pumpe ->oberer und unterer downcomer

2300000 branchl branch

2300001 3 1

2300101 0.00349314 0.2 0 0 90.0 0.20 2.0-5 0.0

2300200 3 1.52811+07 571.739

2301101 220010000 230010000 0.00349314 0.0 0.0

2302101 230010000 260000000 0. 0.0 0.0

2303101 230000000 240000000 0.0034932 5.23 5.23

2301201 1.0967 0 0

2302201 0.0 0 0

2303201 1.0967 0 0

0000000

0001000

0001000

0001000

* komponente 260

* oberer downcomer

2600000 updown annulus

2600001 1

2600101 0.002671 1

2600301 1.235 1

2600601 90.0 1

D:TATMVgWOR.EAWWC.3.DOC .- AM&.T
AIIB GBRA 043 970 BlaftI Page B41

ABB Reaktor GmbH

2600801

2601001

2601201

1.60-6 0.0 1

00000000 1

3 1.49624+07 571.98 0.0 0.0 0.0 1

* komponente 240

* unterer downcomer

2400000 lowdown annulus

2400001

2400101

2400301

2400601

2400801

2400901

2401001

2401101

2401201

2401202

2401203

2401204

2401205

2401206

2401207

2401208

2401209

2401210

2401300

2401301

10

0.00234392

0.6862

-90.0

1.6-6 0.0

0.0 0.0

0000000

0001000

3

3

3

3

3

3

3

3

3

3

1.52838+07

1.52887+07

1.52936+07

1.52964+07

1.53033+07

1.53082+07

1.53131+07

1.53180+07

1.53228+07

1.53277+07

10

10

10

10

9

10

9

571.740

571.742

571.744

571.747

571.749

571.751

571.753

571.755

571.757

571.759

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

1

2

3

4

5

6

7

8

9

10

1

1.0967 0.0 0 9

* komponente 245

* vebindung : zw downcommer und lower plenum

2450000 dwuntplm sngljun

2450101 240010000 102000000 0.0014465 0. 0. 0001000 1.0

2450201 1 1.0967 0. 0.

1.0 1.0

*

*

*

*

kernnotkuehlung

* komponente 910

* 1 borwasserbecken

9100000 bwb tmdpvol

9100101 100. 0. 400. 0.

9100200 3

* time nre~s

0. 0. 0. 0. 0000011

temp

296.5

296.5

9100201

9100202

0. 1.+5

1.+6 1.+5

* komponente 911

* hp injection am ringraum

* flAche: 0.0707 m^2 / 1686 - 0.0000419

9110000 hpi tmdpjun

9110101 910000000 230000000 0.0000419

9110200 1 585 p 230010000

* press flow(1 hpi)

9110201

9110202

9110203

9110204

9110205

9110206

9110207

-1.0

0.

4.90+5

19.61+5

39.23+5

58.84+5

78.46+5

0.0

0.044561

0.043906

0.040629

0.036041

0.029816

0.020644

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

*

*

*

*

*

*

*

(2 hpi)

150.26

150.26

148.05

137.

121.53

100.54

69.61

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

DvAT84MWORMI5OBEA6SmC-o= - AMOM66I
A BB~E ABB Reaktor GmbH

GBRA 043 970 Blatt I Page B42

9110208

9110209

9110210

98.07+5

117.68+5

128.47+5

0.014090

0.006880

0.0

0.

0.

0.

0.

0.

0.

*

*

*

47.51

23.2

0.

0. 0.

0. 0.

0. 0.

* komponente 914

* 1 borwasserbecken

9140000 bwb tmdpvol

9140101 100. 0. 400.

9140200 3

0. 0. 0. 0. 0. 0000011

9140201

9140202

time press

0. 1.+5

1.+6 1.+5

temp

296.5

296.5

* komponente 915

* hp injection ins kalte bein

9150000 hpi tmdpjun

9150101 914000000 230000000 0.0000419

9150200 1 585 p 230010000

9150201

9150202

9150203

9150204

9150205

9150206

9150207

9150208

9150209

9150210

press

-1.0

0.

4.90+5

19.61+5

39.23+5

58.84+5

78.46+5

98.07+5

117.68+5

128.47+5

flow(1 hpi)

0.0

0.044561

0.043906

0.040629

0.036041

0.029816

0.020644

0.014090

0.006880

0.0

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

*

*

*

*

*

*

*

*

*

*

(2 hpi)

150.26

150.26

148.05

137.

121.53

100.54

69.61

47.51

23.2

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

* ==--- eingabe des druckhalters =

* komponente 310 surge-leitung

3100000

*3100101

3100101

3100200

surge snglvol

0.003741 1.0 0 0 0.0 0.0 1.6-6 0.0 0000000

0.003741 1.0 0 0 90.0 1.0 1.6-6 0.0 0000000

2 152.646e+5 0.0

* komponente 315 verbindung surge-dh

3150000

3150101

3150201

su-dh sngljun

327000000 310010000 0.003741 0.0 0.0 0001000

1 0.0 0.0 0.0

1.0 1.0 1.0

* komponente 327 druckhalter unten

3270000

3270101

3270200

dhl snglvol

0.003741 1.0

2 152.616e+5

0.0 0.0 90.0 1.0 1.6e-6 0.0 0000000

0.0

* komponente 313 verbindung 327 - 320

3130000 dh2 sngljun

3130101 327010000 320000000 0.003740 0.0 0.0 0001000 1. 1.

3130201 1 0.0 0.0 0.0

* komponente 320 druckhalter hauptteil

M.DI6EMOSNRC-OODOC - AU*rTnr,
A BB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page B43

3200000

3200001

3200101

3200301

3200601

3200801

3201001

3201101

3201201

3201202

3201203

3201204

3201205

3201206

3201207

3201208

3201209

3201210

3201300

3201301

dh3 pipe

10

0.003741

0.9154

90.0

1.6-6 0.0

0000000

0001000

10

10

10

10

10

9

*

*

*

anzahl der volumen

stroemungsquerschnitt

laenge des volumens

* winkel

* wandrauhigkeit und hydraulischer durchnesser

2

2

2

2

2

2

2

2

2

2

druck

152.559e+5

152.526e+5

152.514e+5

152.505e+5

152. 497e+5

152. 488e+5

152. 479e+5

152. 470e+5

152. 462e+5

152. 453e+5

dampfgehalt

0.0

0.0

0.14

1.0

1.0

1.0

1.0

1.0

1.0

1.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

1

2

3

4

5

6

7

8

9

10

1

0. 0. 0 9

* komponente 325 dampfraum 1.456 m

3250000

3250001

3250101

3250200

3251101

3252101

3251201

3252201

dh4 branch

2 1

0.003741 1.0 0.0 0.0 90.0 1.0

2 152.444e+5 1.0

320010000 325000000 0.003741 0.0

325010000 330000000 0.003741 0.0

0.0 0.0 0.0

0.0 0.0 0.0

1.6-6 0.0

0.0 0001000

0.0 0001000

0000000

*

*

komponente 330 oberster dampfraum dh 0.388 m

3300000 dh5 branch

3300001 0 1

3300101 0.003741 0.2 0.0 0.0 90.0 0.2 1.6e-6

3300200 2 152.438e+05 1.0

0.0 0000000

36500

36501

36502

36503

36503

komponente 365 2 sicherheitsventile

flache: 2 x 0.002694 m^2 / 1686 - 0.0000032

300 dh-si-v valve

.01 330010000 341000000 0.0000032 1. 1. O000

Z01 1 0.0 0.0 0

100 mtrvlv

101 513 538 5.0 0 0

1100 1.0 1.0 1.0

* komponente 341 containment

3410000 cc

3410101 1I

3410200 4

*t

3410201 0

3410202 1

ontain tmdpvol

00.0 0. 400. 0. 0. 0. 0. 0.

ime

.+6

press

1.+5

1.+5

temp

293.

293.

0000011

1.

1.

* ....... ende druckhalter eingabe der komponenten

*:•E•OOt•/GVR,0.O 

/JO.V"

ende der komponenteneingabe

O!OATEMWOFhOSIDEAM MMG5IC~ O - AM-Cr.rT&~
A III ABB Reaktor GmbH

GBRA 043 970 Blatt IPage B44

*

*

*

*

*

*

*

eingabe der heatslabs

*rb ----------- :----- rdb -------------------------------------------------

* komponente 1001

* +++ R4 NiSI NODE 1 METAL SLAB-2 IN. SCH160 PIPE --- 150011

11001000 1 8 2 1 0.029261

11001100 0 1

11001101 2 0.040416 5 0.1166165

11001201 006 2 003 7

11001301 0 7

11001400 0

11001401 571.758 8

11001501 100010000 0 1 0 0.32637 1

11001601 0 0 0 0 1.30071 1 * 1.3006

11001701 0 0 0 0 1

11001801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 1002

* +++ R4 N1S2 LP 1 INCH XXS PIPE --- 150021

11002000

11002100

11002101

11002201

11002301

11002400

11002401

11002501

11002601

11002701

11002801

1 8 2 1 0.048158

0 1

2 0.0656234 5 0.1418234

006 2 003 7

0 7

0

571.754 8

100020000 0 1 0 0.184227 1

0 0 0 0 0.5425412 1 *.54295

0 0 0 0 1

0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

*

*

*

komponente 1003

+++ R4 N1S3 LP 1.25 INCH SCH160 PIPE --- 150031

11003000

11003100

11003101

11003201

11003301

1 8 2 1 0.043672

0 1

2 0.0496824 5 0.125882

006 2 003 7

0 7

11003400 0

11003401 571.758 8

11003501 100010000 0 1 0 0.30342

11003601 0 0 0 0 0.87459

11003701 0 0 0 0 1

11003801 0.0 100.0 100.0 0.0 0.0

* komponente 1101

* +++ R4 N2S1 NODE 2 CV Metal Slab-6

1

1 * 0. 90306

0.0 0.0 1.0 1

In. SCH160 PIPE --- 150041

11010

111011000

11101100

11101101

11101201

11101301

11101400

11101401

1 8 2 1 0.06523

0 1

2 0.083363 5 0.184861

006 2 003 7

0 7

0

571.758 8

110010000 0 1 0 0.90441 1

0.VATMV#0F0SE&BWO5frC.OOfl -AM*.WTds
A 11 ABB Reaktor GmbH GBRA 043 970 Blat I Page B45

11101601 0 0 0 0 2.563087 1 * 2.5628

11101701 0 0 0 0 1

11101801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

• komponente 1102

.+++ R4 N2S2 CV Bottom Head --- 150051

11102000 1 8 2 1 0.0762

11102100 0 1

11102101 2 0.25786 5 0.35936

11102201 006 2 003 7

11102301 0 7

11102400 0

11102401 590.456 8

11102501 120010000 0 1 0 0.07144 1

11102601 0 0 0 0 0.3369118 1 * 0.33696

11102701 0 0 0 0 1

11102801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

• komponente 2701

* +++ R4 N2S3 Node 2 UP and TP Metal Slab --- 150061

12701000 1 8 2 1 0.0445

12701100 0 1

12701101 2 0.058339 5 0.159837

12701201 006 2 003 7

12701301 0 7

12701400 0

12701401 590.818 8

12701501 270010000 0 1 0 1.39187 1

12701601 0 0 0 0 4.999378 1 *5.0007

12701701 0 0 0 0 1

12701801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 1103

.+++ R4 N2S4 Heater Rod Supports --- 150071

11103000 1 5 2 1 0.0

11103100 0 1

11103101 4 0.0074676

11103201 006 4

11103301 0 4

11103400 0

11103401 590.818 5

11103501 0 0 0 0 0.0 1

11103601 280010000 0 1 0 0.35963 1

11103701 0 0 0 0 1

11103901 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

• komponente 1104

.+++ R4 N2S5 Heater Rods --- 150081

11104000 1 8 2 1 0.0

11104100 0 1

11104101 2 0.0113081 5 0.01588

11104201 002 2 006 7

11104301 0 7

11104400 0

11104401 590.818 8

11104501 0 0 0 0 0.0 1

11104601 280010000 0 1 0 0.58529 1

11104701 0 0 0 0 1

11104901 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

c:•ATEMWiOMIC6EA$6 C-OC.3 Aa - ,-Dr.Tds
A ERERG ABB Reaktor GmbH GBRA 043 970 Blatt/ Page B46

* komponente 1301

* +++ R4 NODE 3 Hot Leg Pipe --- 150091

11301000 1 8 2 1 0.034424

11301100 0 1

11301101 2 0.045781 5 0.05849

11301201 006 2 004 7

11301301 0 7

11301400 0

11301401 590.451 8

11301501 130010000 0 1 1 2.48 1

11301601 0 0 0 1 2.48 1

*11301601 0 0 0 0 6.62855 1 *0.0

11301701 0 0 0 0 1

11301801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 1321

* +++ R4 NODE 3 Hot Leg Pipe --- 150091

11321000 16 8 2 1 0.034424

11321100 0 1

11321101 2 0.045781 5 0.05849

11321201 006 2 004 7

11321301 0. 7

11321400 0

11321401 590.42 1

11321402 590.42 2

11321403 590.42 3

11321404 590.42 4

11321405 590.42 5

11321406 590.42 6

11321407 590.42 7

11321408 590.42 8

11321501 132010000 0 1 1 0.9746885 16

11321601 0 0 0 1 0.9746885 16

*11321601 0 0 0 0 6.62855 16 *0.0 1

11321701 0 0 0 0 16

11321801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 16

* komponente 1401

* +++ R4 NODE 4 Hot Leg Pipe --- 150101

11401000 1 8 2 1 0.035357

11401100 0 1

11401101 2 0.046695 5 0.05941

11401201 006 2 004 7

11401301 0 7

11401400 0

11401401 590.391 8

11401501 140010000 0 1 0 0.69128 1

11401601 0 0 0 0 1.16155 1 *0.0 1

11401701 0 0 0 0 1

11401801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 1501

* +++ R4 N5S1 Hot Leg Pipe --- 150111

11501000 1 8 2 1 0.034747

11501100 0 1

11501101 2 0.04624 5 0.058948

11501201 006 2 004 7

11501301 0 7

11501400 0

11501401 590.395 8

0r 'ITMV4RMI0E/k0NRC-0M= - AM.-M.TJrS
A BB ABB Reaktor GmbH GBRA 043 970 Blat I Page B47

11501501 150010000 0 1 0 0.96935 1

11501601 0 0 0 0 1.644494 1 *0-0 1

11501701 0 0 0 0 1

11501801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 1502

* +++ R4 N5S2 SG Inlet Plenum --- 150121

11502000 1 8 2 1 0.04755

11502100 0 1

11502101 2 0.06135624 5 0.162855

11502201 006 2 003 7

11502301 0 7

11502400 0

11502401 590.395 8

11502501 150010000 0 1 0 0.049164 1

11502601 0 0 0 0 0.1683828 1 *0.0

11502701 0 0 0 0 1

11502801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 1503

* +++ R4 N5S3 SG Upper Tubesheets --- 150131

11503000 1 8 2 1 0.00704

11503100 0 1

11503101 7 0.033756

11503201 006 7

11503301 0 7

*11503400 0

11503401 590.395 8

11503501 150010000 0 1 0 0.009058 1

11503601 0 0 0 0 0.04343208 1 *0.0

11503701 0 0 0 0 1

11503801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 1801

* +++ R4 N10Si Lower Tubesheets --- 150301

11801000 1 8 2 1 0.00704

11801100 0 1

11801101 7 0.033756

11801201 006 7

11801301 0 7

11801400 0

11801401 571.737 8

11801501 180010000 0 1 0 0.03268 1

11801601 0 0 0 0 0.156697 1 * 0.0

11801701 0 0 0 0 1

11801801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 1802

* +++ R4 N1OS2 SG Outlet Plenum --- 150311

11802000 1 8 2 1 0.04755

11802100 0 1

11802101 2 0.061356 5 0.162855

11802201 006 2 003 7

11802301 0 7

11802400 0

11802401 571.737 8

11802501 180010000 0 1 0 0.049164 1

11802601 0 0 0 0 0.1683828 1 *0.00

11802701 0 0 0 0 1

11802801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

D:ATEWORD•IA•C,.DOC - MA.-Or*TTs
Al IREG GBRA 043 970 Bratl Page B48 ~jJ3E3ABB Reaktor GmbH

komponente 1803

* +++ R4 N1OS3 Cold Leg Suction Pipe --- 150331

11803000 1 8 2 1 0.03749

11803100 0 1

11803101 2 0.049682 5 0.12588

11803201 006 2 003 7

11803301 0 7

11803400 0

11803401 571.737 8

11803501 180010000 0 1 0 0.31959 1

11803601 0 0 0 0 1.073086 1 *0.16834

11803701 0 0 0 0 1

11803801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 9041

* +++ R4 NODE 11 Cold Leg Suction Pipe --- 150211

19041000 1 8 2 1 0.058217

19041100 0 1

19041101 2 0.071933 5 0.14813

19041201 006 2 003 7

19041301 0 7

19041400 0

19041401 571.74 8

19041501 904010000 0 1 0 0.159329 1

19041601 0 0 0 0 0.405404 1 *0.0

19041701 0 0 0 0 1

19041801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 2001

* +++ R4 NODE 12 RCP --- 150221

12001000 1 8 2 1 0.03353

12001100 0 1

12001101 2 0.0567842 5 0.1329842

12001201 006 2 003 7

12001301 0 7

12001400 0

12001401 571.738 8

12001501 200010000 0 1 0 0.50567 1

12001601 0 0 0 0 2.00555 1 *2.01061

12001701 0 0 0 0 1

12001801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 2201

* +++ R4 NODE 13 Cold Leg Discharge Pipe --- 150231

12201000 1 8 2 1 0.036881

12201100 0 1

12201101 2 0.048768 5 0.124968

12201201 006 2 003 7

12201301 0 7

12201400 0

12201401 571.737 8

12201501 220010000 0 1 0 0.335566 1

12201601 0 0 0 0 1.13703565 1 *1.137133

12201701 0 0 0 0 1

12201801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 2301

* +.+ R4 NODE 13 Cold Leg Discharge Pipe --- 150231

.VATeMWOWcSIBA&itC-o= C - AMOr.7Ws
ABBD ABB Reaktor Gb

GBRA 043 970 Blatt I Page B49

12301000

12301100

12301101

12301201

12301301

12301400

12301401

12301501

12301601

12301701

12301801

1 8 2 1 0.036881

0 1

2 0.048768 5 0.124968

006 2 003 7

0 7

0

571.739 8

230010000 0 1 0 0.335566 1

0 0 0 0 1.13703565 1 *1.137133

0 0 0 0 1

0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 2401

* +++ R4 NODE 17 LDC Metal --- 150271

*12401000

*12401100

*12401101

*12401201

*12401301

*12401400

*12401401

*12401501

*12401601

*12401701

*12401801

1 8 2 1 0.028407

0 1

2 0.0416966 5 0.1178966

006 2 003 7

0 7

0

533.55 8

240010000 0 1 0 1.84235 1

0 0 0 0 7.6462421 1 *4.91608

0 0 0 0 1

0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 2601

* +++ R4 NODE 16 UDC Metal --- 150261

12601000 1 8 2 1 0.028438

12601100 0 1

12601101 2 0.0385572 5 0.1147572

12601201 006 2 003 7

12601301 0 7

12601400 0

12601401 571.98 8

12601501 260010000 0 1 0 0.220738 1

12601601 0 0 0 0 0.890754 1

12601701 0 0 0 0 1

12601801 0.0 100.0 100.0 0.0 0.0 0.0

*0.0

0.0 1.0 1

* komponente 4201

* ..+ R4 NODE 14 SG Shell Metal --- 150251

14201000 1 8 2 1 0.055169

14201100 0 1

14201101 2 0.072756 5 0.174254

14201201 005 2 003 7

14201301 0 7

14201400 0

14201401 590.393 8

14201501 420010000 0 1 0 1.4751795 1

14201601 0 0 0 0 4.6594270 1 *4.66299

14201701 0 0 0 0 1

14201801 0.0 100.0 100.0 0.0 0.0 0.0 0.0 1.0 1

* komponente 3201

* +++ R4 N18S1 PZR Metal --- 150281

13201000 1 8 2 1 0.033528

13201100 0 1

13201101 2 0.044775 5 0.057485

13201201 006 2 004 7

0M1AMW51IOEAMMUMC4OOC -.W
ABB GBRA 043 970 Blatt I Page B50

ABB Reaktor GmbH

13201301 0 7

13201400 0

13201401 616.6 8

13201501 320010000 0 1 0

13201601 0 0 0 0

13201701 0 0 0 0 1

13201801 0.0 100.0 100.0

2.59413 1

4.447732 1 *0.0

0.0 0.0 0.0 0.0

1

1.0 1

* komponente 13202

* +++ R4 N18S2 PZR Surgeline Metal --- 150291

13202000

13202100

13202101

13202201

13202301

13202400

13202401

13202501

13202601

13202701

13202801

1 8 2 1 0.074676

0 1

2 0.079919 5 0.092629

006 2

0 7

0

616.6 8

320010000

0

004 7

0 1

0 0

0 0.28586 1

0 0.3545841 1 *0.0

0 0 0 0 1

0.0 100.0 100.0

1

1.0 1 0.0 0.0 0.0 0.0

* komponente 1701

* waermeplatten an

11701000 52 2 2 1

11701100 0 1

11701101 1 0.007559

11701201 001 1

11701301 0.0 1

11701400 -1

11701401 590.40

11701402 590.40

11701403 590.41

11701404 590.41

11701405 590.41

11701406 590.41

11701407 590.41

11701408 590.41

11701409 590.41

11701410 590.41

11701411 590.41

11701412 590.41

11701413 590.41

11701414 590.41

11701415 590.41

11701416 590.41

11701417 590.41

11701418 590.41

11701419 590.41

11701420 590.41

11701421 590.41

11701422 590.41

11701423 590.40

11701424 590.40

11701425 590.40

11701426 590.39

11701427 590.38

11701428 590.38

11701429 590.37

den heizrohren loop i

0.007047

590.40

590.40

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.41

590.40

590.40

590.39

590.39

590.38

590.37

590.36

D.ZATMVORMI5O8EA8O5JRC-OO=lO -MA-M.r1Tn
ABB GBRA 043 970 Blatt I Page B51

ABB Reaktor GmbH

11701430

11701431

11701432

11701433

11701434

11701435

11701436

11701437

11701438

11701439

11701440

11701441

11701442

11701443

11701444

11701445

11701446

11701447

11701448

11701449

11701450

11701451

11701452

11701501

11701602

11701701

11701801

11701900

11701901

+

590.35 590.35

590.34 590.33

590.32 590.31

590.30 590.29

590.27 590.26

590.24 590.23

590.21 590.19

590.16 590.15

590.11 590.09

590.05 590.02

589.97 589.94

589.88 589.84

589.77 589.72

589.63 589.58

589.47 589.41

589.26 589.19

582.96 582.14

572.73 570.84

571.56 569.89

571.10 569.69

570.68 569.48

569.04 567.88

548.45 545.08

170010000 10000 101

420520000 -10000 111

0 0 0 0

0.0 100.0 100.0 0.0

1 5.802334

0 0.275580

52

0.0 0.0 0.(

52

52

0 1.0 52

0.0 1.0

1

0.015622 100.0

0.305386 1.10

100.0 0.0 0.0 0.0

1.0 52

12401000 10

12401100 0

12401101 2

12401201 006

12401301 0

12401400 0

12401401 573.

12401501 240C

12401601 C

12401701 0

12401801 0.0

* -==== eingabe

8 2 1

1

0.0416966

2 003

7

0.028407

5

7

0.1178966

.55 8

DD10000 0

0

0 0

100. 100.

der heatslabs

1

0

0

0

0

10

0.184235

0.76462421

10

10

0. 0. 0. 0. 1.0 10

fuer den kern ===-=---

* --- eingabe der heizstaebe

* komponente 1 321 heizstabgruppe 1

13210000 1 4 2 1 0.0

13210100 0 1

13210101 3 0.01

13210201 006 3

13210301 1.0 3

13210400 -1

13210401 692.37 684.52 660.74 620.28

13210501 0 0 0 0 0.0 1

13210601 110010000 0 1 0 0.1 1

13210701 31 1.0 0 0 1

13210900 1

13210901 0.03277 100.0 100.0 0.0 0.0 0.0

+ 0.03277 1.1 1.0 1

0.0 1.0

* komponente 1 322 heizstabgruppe 2

13220000 1 4 2 1 0.0

ODoATEMWORM~IOEAMMMRCCODOC - AI-.rags
ABB GBRA 043 970 Blatt I Page B52

ABB Reaktor GmbH

13220100

13220101

13220201

13220301

13220400

13220401

13220501

13220601

13220701

13220900

13220901

+

0 1

3 0.01

006 3

1.0 3

-1

692.51 684.66

0 0 0

110020000 0 1

32 1.0 0

660.88 620.42

0 0.0 1

0 0.1 1

0 1

1

0.03277 100.0 100.0 0.0 0.0

0.03277 1.1 1.0 1

0.0 0.0 1.0

* komponente 1 323 heizstabgruppe 3

13230000 1 4 2 1 0.0

13230100 0 1

13230101 3 0.01

13230201 006 3

13230301 1.0 3

13230400 -1

13230401 692.63 684.78 661.00 620.54

13230501 0 0 0 0 0.0 1

13230601 110030000 0 1 0 0.1 1

13230701 33 1.0 0 0 1

13230900 1

13230901 0.03277 100.0 100.0 0.0 0.0

+ 0.03277 1.1 1.0 1

0.0 0.0 1.0

* komponente 1 324 heizstabgri

13240000 1 4 2 1 0.0

13240100 0 1

13240101 3 0.01

13240201 006 3

13240301 1.0 3

13240400 -1

13240401 692.75 684.90 661.12 6:

13240501 0 0 0 0 0.0

13240601 110040000 0 1 0 0.1

13240701 34 1.0 0 0

13240900 1

13240901 0.03277 100.0 100.0 0.0

+ 0.03277 1.1 1.0 1

uppe 4

20.67

1

1

1

0.0 0.0 0.0 1.0

*

*

*

* eingabe der thermischen eigenschaften der waermestrukturen

*

* tabelle 001: thermische daten fOr sg-tubes

* waermeleitf,,higkeit sg-tubes [w/m-k]

20100100 tbl/fctn 1 1

20100101 273.15 15.0277 338.70 15.3595 366.48

*20100101 310.93 15.0277 338.70 15.3595 366.48

20100102 394.26 16.1336 422.04 16.5567 449.81

20100103 477.59 17.4362 505.37 17.8814 533.15

20100104 560.93 18.7640 588.70 19.1980 616.48

20100105 644.26 20.0526 672.04 20.4777 699.81

20100106 727.59 21.3448 *

* spezifische waermekapazitaet sg-tubes (j/m**3-k]

20100151 273.15 3.7874+6 338.70 3.8546+6 366.48

*20100151 310.93 3.7874+6 338.70 3.8546+6 366.48

20100152 394.26 3.9663+6 422.04 4.0141+6 449.81

20100153 477.59 4.1004+6 505.37 4.1411+6 533.15

20100154 560.93 4.2227+6 588.70 4.2648+6 616.48

15.7316

15.7316

16.9930

18.3248

19.6270

20.9066

3.9137+6

3.9137+6

4.0584+6

4.1817+6

4.3083+6

D.TAT04WiOFJM1EA8WM•RC-00 C - AM-&.TrlS
ABB GBRA 043 970 Blatt I Page B53

ABB Reaktor GmbH

20100155 644.26 4.3536+6

20100156 727.59 4.5006+6

672.04 4.4008+6 699.81 4.4499+6

* tabelle 002 : thermische daten von mgo

* waermeleitfaehigkeit [w/m-k]

20100200 tbl/fctn 1 -1

20100201 310.93 3.98084 810.93 3.98084 *

* spezifische waermekapazitaet [j/m**3-k]

20100251 3.520952+6 3.520952+6

* tabelle 003 : thermische daten von j-m thermo-2

* waermeleitfaehigkeit [w/m-k]

20100300 tbl/fctn 1 1

20100301 273.15 .055386 422.04 .062309

*20100301 310.93 .055386 422.04 .062309

20100302 644.26 .090002 700.00 .090002

* spezifische waermekapazitaet [j/m**3-k]

20100351 273.15 2.17964+5 810.93 2.17964+5

(general insulation)

533.15 .074424

533.15 .074424

* tabelle 004 : thermische daten von kaowool fiber,

* (guard-heating control insulation)

* waermeleitfaehigkeit [w/m-k]

20100400 tbl/fctn 1 -1

20100401 310.93 .050193 477.59 .050193 588.70

20100402 700.00 .072694

.072694

* spezifische waermekapazitaet [j/m**3-k1

20100451 6.8407+4 6.8407+4 6.8407+4 6.8407+4

* tabelle 005 : thermische daten von mild steel

* waermeleitfaehigkeit (w/m-k]

20100500 tbl/fctn 1 -1

20100501 293.15 44.197708 373.15 44.197708 473.15 43.034611

20100502 573.15 41.871513 673.15 39.545318 773.15 38.382220

* spezifische waermekapazitaet [j/(m**3-k]

20100551 3.614844+6 3.943466+6 4.272088+6 4.272088+6 4.929333+6

20100552 5.257955+6

* tabelle 006: thermische daten von stainless steel

waermeleitf,,higkeit [w/m-k]

20100600 tbl/fctn 1 -1

20100601

20100602

20100603

20100604

20100605

20100606

20100607

310.93

422.04

505.37

588.70

755.37

977.59

1227.59

15.82574

17.26718

18.34826

19.42934

21.59151

24.47439

27.71763

366.48

449.82

533.15

644.26

810.93

1060.93

1366.48

16.54646

17.62754

18.70862

20.15007

22.31223

25.55547

29.51943

394.26

477.59

560.93

699.82

894.26

1144.26

16.90682

17.98790

19.06899

20.87079

23.39331

26.63655

* spezifische waermekapazitaet

20100651 3.969300+6 4.063506+6

20100652 4.199145+6 4.242846+6

20100653 4.369412+6 4.410088+6

20100654 4.638273+6 4.708286+6

20100655 4.985924+6 5.064861+6

sg-tubes [j/m**3-k]

4.109475+6 4.154688+6

4.285790+6 4.327979+6

4.489174+6 4.565236+6

4.807636+6 4.900182+6

5.136995+6 5.242097+6

*

*

*

leistungsdaten fuer die kernheizung

D.ZATMWoslM~IOSEICSR=.3=o - AM~r.1Ws
A ABIBI ABB Reaktor GmbH GBRA 043 970 Blat I Page B54

* Daten aus Versuch 1605AA vom 12.04.83

* tabelle 31 heizgruppe 

1

20203100 power 538

20203101 0.0 0.0

20203102 1.0 29.28+3

20203103 145.0 29.28+3

20203104 150.0 24.59+3

20203105 175.2 24.20+3

20203106 334.8 24.20+3

20203107 375.0 23.20+3

20203108 415.2 22.31+3

20203109 454.8 21.86+3

20203110 555.0 20.75+3

20203111 685.2 19.35+3

20203112 805.2 18.33+3

20203113 1045.2 17.07+3

20203114 1405.2 15.34+3

20203115 1645.2 14.61+3

20203116 1885.2 13.89+3

20203117 2085.0 13.22+3

20203118 2205.0 12.83+3

20203119 2710.2 12.27+3

20203120 3235.2 11.71+3

20203121 4299.0 11.27+3

20203122 5299.2 10.76+3

20203123 7020.0 10.21+3

20203124 9142.0 9.65+3

20203125 11362.8 9.20+3

* tabelle 32 heizgruppe 

2

20203200 power 538

20203201 0.0 0.0

20203202 1.0 29.28+3

20203203 145.0 29.28+3

20203204 150.0 24.59+3

20203205 175.2 24.20+3

20203206 334.8 24.20+3

20203207 375.0 23.20+3

20203208 415.2 22.31+3

20203209 454.8 21.86+3

20203210 555.0 20.75+3

20203211 685.2 19.35+3

20203212 805.2 18.33+3

20203213 1045.2 17.07+3

20203214 1405.2 15.34+3

20203215 1645.2 14.61+3

20203216 1885.2 13.89+3

20203217 2085.0 13.22+3

20203218 2205.0 12.83+3

20203219 2710.2 12.27+3

20203220 3235.2 11.71+3

20203221 4299.0 11.27+3

20203222 5299.2 10.76+3

20203223 7020.0 10.21+3

20203224 9142.0 9.65+3

20203225 11362.8 9.20+3

** tabelle 33 heizgruppe 

3

20203300 power 538

20203301 0.0 0.0

20203302 1.0 29.28+3

20203303 145.0 29.28+3

20203304 150.0 24.59+3

DMTMORMIOW"%RC.OO1C 

-AM&ATWS
A RiG ABB Reakior GmbH GBRA 043 970 Blatt I Page B55

20203305 175.2 24.20+3

20203306 334.8 24.20+3

20203307 375.0 23.20+3

20203308 415.2 22.31+3

20203309 454.8 21.86+3

20203310 555.0 20.75+3

20203311 685.2 19.35+3

20203312 805.2 18.33+3

20203313 1045.2 17.07+3

20203314 1405.2 15.34+3

20203315 1645.2 14.61+3

20203316 1885.2 13.89+3

20203317 2085.0 13.22+3

20203318 2205.0 12.83+3

20203319 2710.2 12.27+3

20203320 3235.2 11.71+3

20203321 4299.0 11.27+3

20203322 5299.2 10.76+3

20203323 7020.0 10.21+3

20203324 9142.0 9.65+3

20203325 11362.8 9.20+3

* tabelle 34 heizgruppe 4

20203400 power 538

20203401 0.0 0.0

20203402 1.0 29.28+3

20203403 145.0 29.28+3

20203404 150.0 24.59+3

20203405 175.2 24.20+3

20203406 334.8 24.20+3

20203407 375.0 23.20+3

20203408 415.2 22.31+3

20203409 454.8 21.86+3

20203410 555.0 20.75+3

20203411 685.2 19.35+3

20203412 805.2 18.33+3

20203413 1045.2 17.07+3

20203414 1405.2 15.34+3

20203415 1645.2 14.61+3

20203416 1885.2 13.89+3

20203417 2085.0 13.22+3

20203418 2205.0 12.83+3

20203419 2710.2 12.27+3

20203420 3235.2 11.71+3

20203421 4299.0 11.27+3

20203422 5299.2 10.76+3

20203423 7020.0 10.21+3

20203424 9142.0 9.65+3

20203425 11362.8 9.20+3

* -..-------- ==.... tabellen fuer einspeisecharakteristiken rj/rx

* ( durchfluss - f(gegendruck)

* es ist kein rj-bypass simuliert!

* tabelle 100

* rj - einspeiseventil loop i

* 2 systeme 2 systeme

20210000 power

20210001 -1. 0.

o.VA151EWWFIBSRC4UcDo - AL$&Crlqs
ABB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page B56

20210002

20210003

20210004

20210005

20210006

20210007

20210008

20210009

20210010

0.

13.8+5

34.5+5

50.0+5

55.2+5

65.5+5

75.5+5

86.2+5

100.0+5

0.064914

0.060961

0.055368

0.050415

0.049099

0.045472

0.041189

0.035258

0.

* tabelle 120

* rj - einspeiseventil loop i

*109.445

*102.78

*93.335

*85.

*82.78

*76. 665

*69.445

*59.445

2 systeme

*109.445

*102.78

*93.335

*85.

*82.78

*76.665

*69.445

*59.445

20212000

20212001

20212002

20212003

20212004

20212005

20212006

20212007

20212008

20212009

20212010

power

-1.

0.

13.8+5

34.5+5

50.0+5

55.2+5

65.5+5

75.5+5

86.2+5

100.0+5

1 system

0.

0.064914

0.060961

0.055368

0.050415

0.049099

0.045472

0.041189

0.035258

0.

*

*

*

*

*

*

*

*

berechnung von kontrollvariablen

20503(

20503(

20503(

20503(

20503(

205030

20503(

20503(

berechnung des kollabierten wasserstandes im druckhalter

)00 dh-level sum 1.0 0.0 1

)01 0.0 0.9154 voidf 320010000 0.9154 voidf 320020000

002 0.9154 voidf 320030000 0.9154 voidf 320040000

)03 0.9154 voidf 320050000 0.9154 voidf 320060000

)04 0.9154 voidf 320070000 0.9154 voidf 320080000

)05 0.9154 voidf 320090000 0.9154 voidf 320100000

)06 1.0 voidf 325010000 1.0 voidf 327010000

)07 0.2 voidf 330010000

berechnung der vom sekundaerkreis aufgenommenen waerme

20504000

20504001

20504002

20504003

20504004

20504005

20504006

20504200

20504201

20504202

20504203

20504204

20504205

20504206

20504400

20504401

20504402

20504403

20504404

qzuskll sum 1.0 0.0

0.0 1.0 q 420010000

1.0 q 420040000

1.0 q 420070000

1.0 q 420100000

1.0 q 420130000

1.0 q 420160000

qzuskl2 sum 1.0 0.0

0.0 1.0 q 420190000

1.0 q 420220000

1.0 q 420250000

1.0 q 420280000

1.0 q 420310000

1.0 q 420340000

qzuskl3 sum 1.0 0.0

0.0 1.0 q 420370000

1.0 q 420400000

1.0 q 420430000

1.0 q 420460000

1

1.0

1.0

1.0

1.0

1.0

1.0

1

1.0

1.0

1.0

1.0

1.0

1.0

1

1.0

1.0

1.0

1.0

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

420020000

420050000

420080000

420110000

420140000

420170000

420200000

420230000

420260000

420290000

420320000

420350000

420380000

420410000

420440000

420470000

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

420030000

420060000

420090000

420120000

420150000

420180000

420210000

420240000

420270000

420300000

420330000

420360000

420390000

420420000

420450000

420480000

DVATEMWOMIOSEA80SNRC-MIDW - AS.&.Tgs
ABB GBRA 043 970 Blatt / Page B57

ABB Reaktor GmbH

20504405

20504406

1.0 q 420490000

1.0 q 420520000

1.0 q 420500000 1.0 q 420510000

20504600 qzutot sum 1.0 0.0 1

20504601 0.0 1.0 cntrlvar 40 1.0 cntrlvar 42 1.0 cntrlvar 44 ---------------------------------------------------

* berechnung der vom primaerkreis abgegebenen waerme

20505000

20505001

20505002

20505003

20505004

20505005

20505006

20505200

20505201

20505202

20505203

20505204

20505205

20505206

20505400

20505401

20505402

20505403

20505404

20505405

20505406

20505600

20505601

qabpkll sum 1.0 0.0

0.0 1.0 q 170010000

1.0 q 170040000

1.0 q 170070000

1.0 q 170100000

1.0 q 170130000

1.0 q 170160000

qabpkl2 sum 1.0 0.0

0.0 1.0 q 170190000

1.0 q 170220000

1.0 q 170250000

1.0 q 170280000

1.0 q 170310000

1.0 q 170340000

qabpkl3 sum 1.0 0.0

0.0 1.0 q 170370000

1.0 q 170400000

1.0 q 170430000

1.0 q 170460000

1.0 q 170490000

1.0 q 170520000

1

1.0

1.0

1.0

1.0

1.0

1.0

1

1.0

1.0

1.0

1.0

1.0

1.0

1

1.0

1.0

1.0

1.0

1.0

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

170020000

170050000

170080000

170110000

170140000

170170000

170200000

170230000

170260000

170290000

170320000

170350000

170380000

170410000

170440000

170470000

170500000

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

q

170030000

170060000

170090000

170120000

170150000

170180000

170210000

170240000

170270000

170300000

170330000

170360000

170390000

170420000

170450000

170480000

170510000

qabtot sum 1.0 0.0 1

0.0 1.0 cntrlvar 50 1.0 cntrlvar 52 1. 0 cntrlvar 54

* berechnung des inventars im dampferzeuger

* de

20511000

20511001

20511002

20511003

20511004

20511005

20511006

20511200

20511201

20511202

20511203

20511204

20511205

20511206

20511400

20511401

20511402

20511403

20511404

20511405

20511406

20511600

20511601

i

delmassl sum 0.001459 0.0

0.0 1.0 rho 420010000 1.0 rho

1.0 rho 420040000 1.0 rho

1.0 rho 420070000 1.0 rho

1.0 rho 420100000 1.0 rho

1.0 rho 420130000 1.0 rho

1.0 rho 420160000 1.0 rho

delmass2 sum 0.001459 0.0

0.0 1.0 rho 420190000 1.0 rho

1.0 rho 420220000 1.0 rho

1.0 rho 420250000 1.0 rho

1.0 rho 420280000 1.0 rho

1.0 rho 420310000 1.0 rho

1.0 rho 420340000 1.0 rho

delmass3 sum 0.001459 0.0

0.0 1.0 rho 420370000 1.0 rho

1.0 rho 420400000 1.0 rho

1.0 rho 420430000 1.0 rho

1.0 rho 420460000 1.0 rho

1.0 rho 420490000 1.0 rho

1.0 rho 420520000

1

420020000

420050000

420080000

420110000

420140000

420170000

1

420200000

420230000

420260000

420290000

420320000

420350000

1

420380000

420410000

420440000

420470000

420500000

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

rho

rho

rho

rho

rho

rho

rho

rho

rho

rho

rho

rho

rho

rho

rho

rho

rho

420030000

420060000

420090000

420120000

420150000

420180000

420210000

420240000

420270000

420300000

420330000

420360000

420390000

420420000

420450000

420480000

420510000

demasse sum 1.0 0.0 1

0.0 1.0 cntrlvar 110 1.0 cntrlvar 112 1.0 cntrlvar 114

* berechnung des wasserstandes im dampferzeuger - sek.

DATBAWORDISCEABO5WRC-=~DOC -A&Or.T#T
ABB GBRA 043 970 Blatt / Page B58

ABB Reaktor GmbH

* de

20521000

20521001

20521002

20521003

20521004

20521005

20521006

20521200

20521201

20521202

20521203

20521204

20521205

20521206

20521400

20521401

20521402

20521403

20521404

20521405

20521406

20521600

20521601

i

delevell sum

0.0 1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

deleve12 sum

0.0 1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

delevel3 sum

0.0 1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

0.305386

420010000

420040000

420070000

420100000

420130000

420160000

0.305386

420190000

420220000

420250000

420280000

420310000

420340000

0.305386

420370000

420400000

420430000

420460000

420490000

420520000

0.0 1

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

0.0 1

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

0.0 1

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

420020000

420050000

420080000

420110000

420140000

420170000

420200000

420230000

420260000

420290000

420320000

420350000

420380000

420410000

420440000

420470000

420500000

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

420030000

420060000

420090000

420120000

420150000

420180000

420210000

420240000

420270000

420300000

420330000

420360000

420390000

420420000

420450000

420480000

420510000

delevel sum 1.0 0.0 1

0.0 1.0 cntrlvar 210 1.0 cntrlvar 212 1.0 cntrlvar 214

* berechnung des wasserstandes im dampferzeuger - prim.

* de i

20522100 d

20522101 0

20522102

20522103

20522104

20522105

20522106

20522200 d

20522201 0

20522202

20522203

20522204

20522205

20522206

20522400 d

20522401 0

20522402

20522403

20522404

20522405

20522406

elevell sum

.0 1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

elevel2 sum

.0 1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

eleve13 sum

.0 1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

0.305386

170010000

170040000

170070000

170100000

170130000

170160000

0.305386

170190000

170220000

170250000

170280000

170310000

170340000

0.305386

170370000

170400000

170430000

170460000

170490000

170520000

0.0 1

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

0.0 1

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

0.0 1

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

170020000

170050000

170080000

170110000

170140000

170170000

170200000

170230000

170260000

170290000

170320000

170350000

170380000

170410000

170440000

170470000

170500000

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

1.0

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

voidf

170030000

170060000

170090000

170120000

170150000

170180000

170210000

170240000

170270000

170300000

170330000

170360000

170390000

170420000

170450000

170480000

170510000

20522600 delevel sum 1.0 0.0 1

20522601 0.0 1.0 cntrlvar 221 1.0 cntrlvar 222 1.0

20522602 4.691 voidf 150010000

* berechnung des wasserstandes im hei~en bein

cntrlvar 224

20523000

20523001

20523002

20523003

20523004

20523005

hilevell sum

0.0 1.0 voidf

1. 0 voidf

1. 0 voidf

1. 0 voidf

1. 0 voidf

0.974688!

132010000

132040000

132070000

132100000

132130000

5 0.0 1

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

1.0 voidf

132020000

132050000

132080000

132110000

132140000

1.0

1.0

1.0

1.0

1.0

voidf

voidf

voidf

voidf

voidf

132030000

132060000

132090000

132120000

132150000

M.DTENWOR51O8MaAOSNRC-0-mo MA*&TgTr
ABIB ABB Reaktor GmbH

GBRA 043 970 Blatt / Page B59

20523006

20523200

20523201

20523202

1.0 voidf 132160000

hilevel sum

-0.775004 1.0

2.480

1.0 0.0 1

cntrlvar 230 3.271

voidf 130010000

voidf 140010000

*

*

berechnung des wasserstandes im kernbereich

20524000

20524001

20524002

20524003

20524004

20524005

20524200

20524201

colevell sum

0.0 0.2

0.375

0.4875

0.4875

1.091

1.0

voidf

voidf

voidf

voidf

voidf

0.0

102010000

100020000

110020000

110040000

110060000

1

1.92

0.4875

0.4875

1.091

0.2

voidf

voidf

voidf

voidf

voidf

100010000

110010000

110030000

110050000

120010000

colevell sum 1.0

-7.445 1.0 cntrlvar 240

0.0 1

20524300 colevell sum 1.0

20524301 0.0 1.470 voidf

0.0 1

270010000

20524400 delevel sum 1.0 0.0 1

20524401 0.0 1.0 cntrlvar 242 1.0 cntrlvar 243

20524500

20524501

colevell sum 1.0

0.0 1.6345 voidf

0.0 1

280010000

20524600 delevel sum 1.0 0.0 1

20524601 0.0 1.0 cntrlvar 244 1.0 cntrlvar 245

20514000 mflow sum 1.0 0.0 1

20514001 0.0 1.0 mflowj 911000000 1.0 mflowj 915000000

*

*

berechnung druckabfall ueber dem core

*20506000 dpcore sum 1.0 0.0 1

*20506001 0.0 1.0 p 110010000 -1.0 p 110060000

* berechnung druckabfall ueber vv

20507000 dpvv sum 1.0 0.0

20507001 0.0 1.0 p 270010000

20526100 vv-mf integral 1.0

20526101 mflowj 265000000

20526200 leck-mf integral 1.0

20526201 mflowj 905000000

20526300 hp-mf integral 1.0

20526301 mflowj 911000000

1

-1.0 p 260010000

0.0 1

0.0 1

0.0 1

20526400 0.0 1

20526401

20526500

20526501

hp-mf integral 1.0

mflowj 915000000

hp-mf sum 1.0

0.0 1.0 cntrlvar 26:3

0.0 1

1.0 cntrlvar 264

20526600 hp-mf integral 1.0 0.0 1

20526601 inflowj 921000000

20550000 hp-mf integral 1.0

20550001 cntrlvar 100

0.0 1

ftlcAnMWaRMI51EA8WJoM=G -D AM.I
A IGBRA 043 970 Blatt I Page B60

ABB Reaktor GmbH

20550100 hp-mf integral 1.0 0.0 1

20550101 cntrlvar 46

20550200 hp-mf sum 1.0 0.0 1

20550201 0.0 1.0 mflowj 905000000

20550300 hp-mf sum 1.0 0.0 1

20550301 0.0 1.0 mflowj 911000000 1.0 mflowj 915000000

20550400 hp-mf sum 1.0 0.0 1

20550401 0.0 1.0 mflowj 921000000

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

* berechnung der leistungszufuhr durch die heat slabs im druckhalter

20507700 qzu0l sum 1.0 0.0 1

20507701 0.0 1.0 q 320010000 1.0 q 320020000 1.0 q 320030000

20507702 1.0 q 320040000 1.0 q 320050000 1.0 q 320060000

20507703 1.0 q 320070000 1.0 q 320080000 1.0 q 320090000

20507704 1.0 q 320100000

20507900 qzu03 sum 1.0 0.0 1

20507901 0.0 1.0 q 325010000 1.0 q 327010000

20507902 1.0 q 330010000

20508000 qzudhhs sum 1.0 0.0 1

20508001 0.0 1.0 cntrlvar 77 1.0 cntrlvar 79

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

* zugefuehrte energie core

20510000 qzucor sum 1.0 0.0 1

20510010 0.0 1.0 q 110010000 1.0 q 110020000 1.0 q 110030000

20510011 1.0 q 110040000

20509100 qzucor sum 1.0 0.0 1

20509110 0.0 1.0 q 110010000

20509200 qzucor sum 1.0 0.0 1

20509210 0.0 1.0 q 110020000

20509300 qzucor sum 1.0 0.0 1

20509310 0.0 1.0 q 110030000

20509400 qzucor sum 1.0 0.0 1

20509410 0.0 1.0 q 110040000

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

* eingestroemte masse in den reaktorkern

20526700 rein-mf integral 1.0 0.0 1

20526701 mflowj 105000000

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

* ausgestroemte masse aus dem reaktorkern

20526800 reout-mf integral 1.0 0.0 1

20526801 mflowj 120010000

DMTMOIBASR-U AM*.Tns
A BB ABB Reakor GmbH GBRA 043 970 Blatt I Page B61

20526900 kern-mf sum 1.0 0.0 1

20526901 0.0 1.0 cntrlvar 267 -1.0 cntrlvar 268

* temperaturabsenkung - 28 k/h

20529000 deltap sum 1.0 0.0 1

20529001 0.0 1.0 p 440010000 -1.0 p 480010000

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

* berechnung der einspeiseraten von rj und rx

* -------------- rj loop i-----------------------------------

*20520000 funcrjl function 1.0 0.0 1

*20520001 p 420070000 100

*20520500 durchrjl mult 1.0 0.0 1

*20520501 cntrlvar 200 vlvarea 604

* -------------- rj loop ii----------------------------------

*20521000 funcrj2 function 1.0 0.0 1

*20521001 p 422070000 110

*20521500 durchrj2 mult 1.0 0.0 1

*20521501 cntrlvar 210 vlvarea 606

* ----------- rj + rx loop i------------------------------------

20522000 funcrxl function 1.0 0.0 1

20522001 p 420070000 120

20522500 durchrxl mult 1.0 0.0 1

20522501 cntrlvar 220 vlvarea 624

* ---------- rj + rx loop ii----------------------------------

*20523000 funcrx2 function 1.0 0.0 1

*20523001 p 422070000 130

*20523500 durchrx2 mult 1.0 0.0 1

*20523501 cntrlvar 230 vlvarea 626

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

end of case

DMDATaMWOAMIhMEAW%4RC4cc.co - M&Er.lWs
A BB ABB Reaktor GmbH

GBRA 043 970 Blatt I Page B62

RELAP5 MOD 3.2 Input Deck for the GERDA Test 1605AA Post Test Restart

Calculation

* relap5/mod3.2

- title

* Inputfile: abx4. inp

* Datum: 28.04.98

100

101

103

*103

105

201

202

203

204

205

LeckflAche: 75% ab 2600 s

Hochdruckeinspeisung als Funktion der Zeit, aus ABX.INP

restart transnt

run

11824 ncmpr•

602 ncmpre.

5.0 6.0

200.0 1.0-8

2000.0 1.0-8

4000.0 1.0-8

8000.0 1.0-8

12000.0 1.0-8

ess

ss

0.25

0.25

0.25

0.25

0.25

7

7

7

7

7

2

4

20

20

20

800

800

4000

4000

4000

800

800

4000

4000

4000

9050000

9050101

1.0

9050201

9050300

9050301

9110000

9110101

9110200

9110201

9110202

9110203

9110204

9110205

9110206

9110207

break valve

102000000 906000000

1 0.035 0. 0.

mtrvlv

501 513 66.67 1.

hpi tmdpjun

910000000 230000000

1

2600.0

3100.0

3600.0

6600.0

9700.0

11300.0

12000.0

0.0195

0.0312

0.0335

0.0320

0.0312

0.0310

0.0315

0

0

0

0

0

0

0

0.0000004448 0.0 0.0 0000100 1.0 1.0

0

0.0000419

0

0

0

0

0

0

0

0.0000419

0

0

0

0

0

0

0

9150000 hpi tmdpjun

9150101 914000000 230000000

9150200 1

9150201 2600.0 0.0195 0

9150202 3100.0 0.0312 0

9150203 3600.0 0.0335 0

9150204 6600.0 0.0320 0

9150205 9700.0 0.0312 0

9150206 11300.0 0.0310 0

9150207 12000.0 0.0315 0

end of case

OM.DTMa~VWORSt08EMOSNRC4O3O -AM.Dr.1Tgs
NRC FORM 325 US. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

(24W) (Assigned by NRCM Add Vol. Supp, Rev., NROM 1102, end Addendum Numbers If any.) 3W1, 3= BIBUOGRAPHIC DATA SHEET

2. TrILE AND SUBTTLEI NUREGAIA-0166

RELAPS/MOD3.2 Assessment Using GERDA Small Break Test 1605AA

3. DATE REPORT PUBYSHED

July 1999

4. FIN OR GRANT NUMBER

5. AUTHOR(S) 6. TYPE OF REPORT

W. Tietsch Technical

7. PERIOD COVERED cuiv. Dafes)

8. PERFORMING ORGANIZATION - NAME AND ADDRESS WNMC. povieDivan, Of'eorRegpn. U.S. MicewRegumorw•.son and mani.-W address, irecer.

-ovid name n ma-nV addrss)

ABB Reaktor GmbH

Dudenstrasse 44

D-68176 Mannheim, Germany

9. SPONSORIN ORGANIZATION - NAME AND ADDRESS 01`NRC, 4Wp "Samne* abolve', f~cnrio, prode NRC0W oftre orfteko U.S. Ak ~Reubf, C4MffW.•bA

and maet addnmsJ

Division of Systems Technology

Office of Nuclear Reactor Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

10. SUPPLEMENTARY NOTES

11. ABSTRACT r" waf aoer1)

This report presents the results of RELAP5/MOD3.2 assessment on the integral (composite) GERDA Test 1605 AA which features

a complete sequence of a 10 cm2 Reactor Vessel Leak transient conducted on April 12,1983. The purpose of the assessment

analysis was to determine whether the tested RELAP version can predict the major phenomena of this complex transient and to

provide some useful information both to code developers and analysts for the application on SBLOCA transients In

'Once-Through-Steam-Generator' Plants. The Small Break Loss of Coolant Accident (SBLOCA) Test Facility GERDA (Geradrohr

Dampferzeuger Anlage) was designed to evaluate the post SBLOCA thermal-hydraulic events expected to occur in the German

Mulheim-Kadich plant The scaled in volume 1:1 in height Test Facility was buit and tested by B&W at the Alliance Research

Centre (ARC) under contract of BBR (Brown Boveri Reaktor GmbH) now ABB Reaktor GmbH. The objective of the whole test

program was to obtain detailed experimental data for the evaluation of single and composite SBLOCA phenomena and for the

verification and refinement-of the analytical tools and models used to predict plant performance during SBLOCA transients.

Additionally, this report presents some base calculations identified as conditioning calculations of OTSG stready state and transient

behaviour which is one of the essentials for the prediction of phenomena observed in the SBLOCA scenarios.

12. KEY WORDS/DESCRIUPTORS -t I word s 1 e at wMassteseacher & tecatr in =ng etor.) I&. AVA•LABZJY STATEMENT

RELAP5/MOD3.2 unlimited

GERDA 14. s cAss..xnoN

Small Break Loss of Coolant Accident (Ths PFW)

unclassified

(Th•, Rp

unclassified

15. NUMBER OF PAGES

16. PRICE

iRC FOM 2I F5 IhsIIiwsaetnua1 mde yEit aes om~kc

NRC FORM 335 (24M) This ftm vm electronically V "d - - by Elite Weral Fornm kc.


~on recycled~

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