NUREG/IA-0422 

International 

 Agreement Report

Transient Analysis of the Research Reactor MARIA 

MC Fuel Elements Using RELAP5 Mod 3.3 

Prepared by:

M. Dabrowski, P. Domitr, E. Staron

 

 

Panstwowa Agencja Atomistyki

(National Atomic Energy Agency)

Krucza 36

00-522 Warszawa, POLAND

 

A. Calvo, NRC Project Manager

 

 Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

Manuscript Completed: November 2012

Date Published: March 2013

Prepared as part of 

The Agreement on Research Participation and Technical Exchange

Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Published by

U.S. Nuclear Regulatory Commission
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NUREG/IA-0422 

International 

 Agreement Report

Transient Analysis of the Research Reactor MARIA 

MC Fuel Elements Using RELAP5 Mod 3.3 

Prepared by:

M. Dabrowski, P. Domitr, E. Staron

 

 

Panstwowa Agencja Atomistyki

(National Atomic Energy Agency)

Krucza 36

00-522 Warszawa, POLAND

 

A. Calvo, NRC Project Manager

 

 Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

Manuscript Completed: November 2012

Date Published: March 2013

Prepared as part of 

The Agreement on Research Participation and Technical Exchange

Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Published by

U.S. Nuclear Regulatory Commission

iii

ABSTRACT

The new fuel type in the Research Reactor ‘Maria’ is undergoing a test procedure. Thermalhydraulic calculations using RELAP have been applied in order to cross-check the results 

obtained using a specialized thermal-hydraulic ‘SN’ code. Nodalization of the fuel element has 

been developed and calculations have been performed. LOFA and RIA cases have been 

analysed and compared showing good agreement between the two codes.

v

CONTENTS

Page

ABSTRACT ..................................................................................................................................iii

FIGURES..................................................................................................................................... vii

TABLES...................................................................................................................................... viii

EXECUTIVE SUMMARY ........................................................................................................... ix

ABBREVIATIONS ..................................................................................................................... xiii

1 INTRODUCTION............................................................................................................... 1-1

2 FACILITY DESCRIPTION................................................................................................ 2-1

2.1 MARIA research reactor technical information ...................................................... 2-1

2.2 Fuel channel with fuel element technical information:.......................................... 2-2

3 CODE INPUT AND MODEL DESCRIPTION ............................................................... 3-1

3.1 Nodalization................................................................................................................. 3-1

3.2 Heat structures............................................................................................................ 3-2

3.3 Limitation of the model and errors ........................................................................... 3-3

4 RESULTS........................................................................................................................... 4-1

4.1 Steady state evaluation ............................................................................................. 4-1

4.2 LOFA - Loss of flow in the fuel channel cooling system....................................... 4-6

4.3 Slow reactivity insertion accident on low power level ......................................... 4-10

4.4 Fast reactivity insertion accident on low power level.......................................... 4-13

4.5 Slow reactivity insertion accident during normal operation of reactor.............. 4-15

4.6 Fast reactivity insertion accident during reactor normal operation................... 4-19

5 RUN STATISTICS............................................................................................................. 5-1

6 CONCLUSIONS................................................................................................................ 6-1

7 REFERENCES.................................................................................................................. 7-1

Appendix A – Technical information on the Research Reactor MARIA .......................... A-1

Appendix B – Input file. ........................................................................................................... B-1

vii

FIGURES

Page

Figure 1. Simplified scheme of the Research Reactor ‘MARIA’ core configuration............... 2-1

Figure 2. Simplified scheme of the fuel channel with an MC fuel element ............................ 2-2

Figure 3. Nodalization scheme of the MC fuel element. ....................................................... 3-1

Figure 4. Positioning of mesh points in each fuel pipe – grey colour clad material, red colour -

fuel........................................................................................................................ 3-2

Figure 5. Placement of measurement points........................................................................ 3-2

Figure 6. Temperature distribution on ICIP of each fuel pipe ............................................... 4-2

Figure 7. Temperature distribution on ECIP of each fuel pipe .............................................. 4-2

Figure 8. Temperature distribution on ICEP of each fuel pipe .............................................. 4-3

Figure 9. Temperature distribution on ECEP of each fuel pipe............................................. 4-3

Figure 10. Water temperature distribution in gaps between fuel pipes. In – filler gap............. 4-4

Figure 11. Maximum temperature axial distribution in fuel pipe no. 6. Yellow dots – calculation 

points in fuel pipe, red – fuel, blue – cladding........................................................ 4-4

Figure 12. Heat flux distribution on inner side of fuel pipes. ................................................... 4-5

Figure 13. Heat flux distribution on outer side of fuel pipes .................................................... 4-5

Figure 14. Cladding and water temperature changes. SN code: water and fuel element outlet 

temperature, RELAP5: water I – fuel element outlet temperature, water II - fuel 

channel outlet temperature ................................................................................... 4-8

Figure 15. Cladding and water temperature changes. SN code: water and fuel element outlet 

temperature, RELAP5: water I – fuel element outlet temperature, water II - fuel 

channel outlet temperature. Wider scale range..................................................... 4-8

Figure 16. ONBR parameter changes.................................................................................... 4-9

Figure 17. Reactivity changes. RELAP5: total reactivity change; water and fuel: reactivity 

change due to coolant and fuel temperature reactivity coefficients...................... 4-12

Figure 18. Power changes of fuel element for SRIA on low power level............................... 4-12

Figure 19. Power changes of fuel element for FRIA on low power level............................... 4-14

Figure 20. ONBR parameter changes.................................................................................. 4-14

Figure 21. Reactivity changes - RELAP5 calculations: i) change of reactivity: total re-activity 

change, ii) water: change due to coolant temperature reactivity coefficients, iii) fuel: 

change due to fuel temperature reactivity coefficient........................................... 4-15
viii

Figure 22. Power changes of fuel element for SRIA on nominal power level........................ 4-17

Figure 23. Cladding and water temperature changes. RELAP5 and SN codes: cladding –

cladding temperature, water – fuel element outlet temperature........................... 4-17

Figure 24. ONBR parameter changes.................................................................................. 4-18

Figure 25. Reactivity changes. RELAP5 and SN codes: change of reactivity - total re-activity 

change, water - change due to coolant temperature reactivity coefficients, fuel -

change due to fuel temperature reactivity coefficients......................................... 4-18

Figure 26. Power changes of fuel element for FRIA on nominal power level........................ 4-20

Figure 27. ONBR parameter changes.................................................................................. 4-21

Figure 28. Cladding and water temperature changes. RELAP5 and SN codes: cladding –

cladding temperature, water I – fuel element outlet temperature, water II - fuel 

channel outlet temperature ................................................................................. 4-21

Figure 29. Reactivity changes. RELAP5 and SN codes: change of reactivity - total reactivity 

change, water - change due to coolant temperature reactivity coefficients, fuel -

change due to fuel temperature reactivity coefficients......................................... 4-22

Figure 30. Calculation time for various cases......................................................................... 5-1

TABLES

Page

Table 1. Distribution of heat generation on fuel pipes and comparison of heat generation with 

content of uranium ................................................................................................ 3-3

Table 2. Comparison of results for two scenarios ............................................................... 4-6

Table 3. Sequence of events for LOFA............................................................................... 4-7

Table 4. Distribution of calculated top temperatures on fuel pipes ...................................... 4-7

Table 5. Comparison of results for second temperature peak........................................... 4-10

Table 6. Comparison of results for SRIA on low power level............................................. 4-11

Table 7. Comparison of results for FRIA on low power level............................................. 4-13

Table 8. Comparison of results for SRIA during normal operation .................................... 4-16

Table 9. Comparison results for FRIA during normal operation......................................... 4-19
ix

EXECUTIVE SUMMARY

In accordance with the international agreement on GTRI (Global Threat Reduction Initiative) 

Poland agreed to change the fuel type in the MARIA research reactor in Świerk from Highly 

Enriched Uranium (HEU) fuel to Low Enriched Uranium fuel (LEU). The new fuel MC5-485 – in 

short MC fuel - consists of 19,75% of 235-U. At this stage several new MC elements have been 

inserted into the reactor core and are under a test procedure.

Prior to this test, thermal-hydraulic effects have been calculated by the operator using a 

specialized computer code called ‘SN’. The SN code is capable of performing thermal-hydraulic 

calculations of the fuel elements behaviour and has been verified and validated for the research 

reactor MARIA only.

The Polish National Atomic Energy Agency (PAA) has decided to try to cross-check the results 

of the analysis using the RELAP5 code although it is aware that the results of the analysis at 

this stage might need further elaboration and additional calculations. However an important aim 

is to gain experience in performing analysis using RELAP5 and to judge whether it is applicable 

and to what extent to the analysis of the research reactor.

The National Centre for Nuclear Research who is the operator of the research reactor MARIA 

has provided the results of two types of accidents: a Reactivity Initiated Accident (RIA) and Loss 

of Flow Accident (LOFA). The analysis of RIA was divided into four scenarios: two for reactor 

low power level operation (possible during start-up of the reactor or during work with low power 

level – 10 kW) and two for normal operation with maximum allowed power. Both cases were 

performed for slow and fast reactivity insertion. The SN code models the fuel element only. It 

does not include the possibility to model the whole reactor together with the safety systems. As 

a consequence of this limitation no analyses of the Loss Of Coolant Accident (LOCA) have been 

supplied as yet. Using RELAP should change this and enable the regulatory body to perform a 

LOCA analysis as well.

The Regulatory Body has cross checked the analyses made and presented by the operator and 

has provided the comparison of results in this report. Due to other limitations of the SN code, 

the comparison is rather limited. Only a small number of parameters is included in the SN 

output. Thus, only those could be compared.

The presented results of calculations do not include errors and sensitivity studies. However the 

scenario analysed for the purpose of this document was made with conservative assumptions. 

The model used for this calculation was limited to a model of the fuel element only. Other 

elements of the reactor systems were not included. As a consequence it was necessary to: 

• omit influence of reactivity coefficients of the coolant in reactor pool and beryllium blocks 

positioned around the analysed fuel channel; the omitted thermal reactivity coefficients 

are positive but during postulated accidents, the increase of the temperature of the 

beryllium blocks and water of pool is very low,

• omit heat transfer between the fuel channel and water of the reactor pool; the influence 

of this factor is very small due to the very small difference in temperatures between 
x

water in the outer part of the fuel channel and the water in the pool (i.e. heated water 

flows in the internal part of fuel channel).

Following an introduction in chapter 1, the report covers a short description of the Research 

Reactor ‘Maria’ including the fuel channel and the fuel element presented in chapter 2. 

Additional information concerning the RR Maria is supplied in Appendix A. 

The nodalization model is presented in chapter 3 and includes a description of the fuel channel 

and heat structures. The input data file is attached in Appendix B.

The results of the calculations are presented in chapter 4 mostly on figures. They begin with the 

steady state evaluation which is followed by a loss of flow in the fuel channel analysis. Further 

analyses cover the slow reactivity insertion accident on low power level, fast reactivity insertion 

accident on low power level, slow reactivity insertion accident during reactor normal operation 

and finally fast reactivity insertion accident during reactor normal operation. 

In chapter 5 a brief information on run statistics is presented. 

Finally a summary of the results is presented in chapter 6.

As already mentioned, initial calculations were performed for steady-state conditions. The newly 

created model of the reactor with the new fuel elements for RELAP was used and compared 

with the results of steady state calculations received from the SN code. The limitations of the SN 

code does not allow to perform detailed comparisons however peak cladding temperatures and 

heat flux were compared.

The steady state was calculated for the reactor normal operation deviated from full power.

The conditions that were used in the simulation were chosen to simulate work of the fuel 

channel during normal operation with safety parameters equal to warning signals. In order to 

have such conditions the mass flow was reduced to 90% of nominal value and thermal power 

was increased to 110% of the nominal value.

The results received were satisfactory.

Loss of flow in the fuel channel cooling system is possible in case of the loss of power in the 

pump system. As a result a sudden decrease of pressure occurs in the cooling channel that 

leads to the initiation of the emergency signal and shutdown of the reactor. Furthermore, after 

the loss of flow a rapid increase of fuel clad temperature and cooling temperature in gaps 

between fuel pipes occurs. According to the scenario a few seconds after the loss of power in 

the pump system, the work of a backup pump should be initiated powered by accumulator 

batteries however operating at a lower speed – 1500 r/s. After the reactor shutdown and before 

the flow is stabilized another small temperature jump can be detected. 

The highest outer clad temperature calculated with the RELAP5 code was 432K (outer layer 

temperature – 440K). The temperature calculated with the SN code was 433.4K. Both codes 

calculated the highest temperature in the same place – on the internal side of pipe number 6. 

In case when the operator undertakes incorrect actions or a malfunction of the reactivity 

regulation system occurs, it is possible that as a result, positive reactivity is inserted into the 

core with the maximum reactivity speed 0.04$/s. This scenario was checked for low power level 

conditions. This scenario has the lowest impact on the fuel elements. The temperature peaks of 
xi

water and clad are very small - smaller than fluctuations of temperature during normal operation 

of the reactor. 

One of the important scenarios addressed in the supplementary document is the fast inflow of 

cold water into the core resulting in a sudden increase of reactivity. The negative reactivity 

coefficients lead to the increase of power in the fuel elements. The scenario analysis was 

performed for low power. The results received were satisfactory. 

The slow reactivity insertion accident during normal operation was very similar to the slow 

reactivity insertion accident on low power. Also here the results were satisfactory. 

A break of control rods is another scenario analysed. The break of control rods leads to fast 

insertion of positive reactivity into the reactor. It is assumed that the maximum insertion of 

positive reactivity is equal to 1.5$ with the top speed of insertion 4$/s.

The main differences in the results between RELAP and the SN code are due to the different 

models of reactor kinetics. RELAP5 uses the point kinetic model and this model was applied to 

the RIA analysis. In case of the SN code a more pessimistic model was used.

Summarizing the analysed cases it can be stated that most of the results of the simulation for 

the research reactor MARIA obtained using the RELAP5 code, showed that there are no big 

differences between the results achieved by the validated SN and the RELAP5 codes. Only in 

one case (RIA with fast reactivity insertion with maximum power level) there is the opportunity to 

exceed the lowest allowed level of the ONBR parameter. Exceeding this parameter can cause 

the onset of boiling of the coolant in the gap between the fuel pipes. In the analysed case, the 

duration of time when ONBR is lower than 1.2 is very short (about 0.35s) and should not cause 

any damage to the fuel and clad material. In the fast RIA scenario, the power jump during the 

insertion of positive reactivity was stopped by the negative reactivity coefficients (fuel and 

coolant) before insertion of the safety and control rods into the core could be initiated. 

In other simulated scenarios, no opportunity to exceed the ONBR parameter or temperature 

limit of clad – 452K occurred. 

In the analysed LOFA scenario, the calculations showed that enough cooling capability is 

provided even when only one pump is working with a lower rotation speed than the normally 

required two pumps. 

The content of this report does not cover all possible accident conditions that should be 

analysed for the research reactor. Further analysis will be necessary. A comparison of the SN 

and RELAP5 codes showed that RELAP5 can be used in the safety analysis for the research 

reactor MARIA.

xiii

ABBREVIATIONS

ECEP external side of clad on the external side of pipe

ECIP external side of clad on the internal side of pipe

HEU highly enriched Uranium

ICEP internal side of clad on the external side of pipe

ICIP internal side of clad on the internal side of pipe

LEU Low enriched Uranium

LOFA Loos of Flow Accident

NCBJ Narodowe Centrum Badań Jądrowych (National Centre for Nuclear Research)

ONBR Onset of Nucleate Boiling Ratio

PAA Państwowa Agencja Atomistyki (National Atomic Energy Agency of Poland)

PAR automatic regulation rod

PK control rods

PB safety rods

REP moving type fuel elements

RIA Reactivity Initiated Accident

RR research reactor

SN name of computer code used for RR ‘Maria’ calculations

1-1

1 INTRODUCTION

Fulfilling the international agreement on GTRI (Global Threat Reduction Initiative) Poland 

agreed to change the fuel type in the MARIA research reactor in Świerk from Highly Enriched 

Uranium (HEU) fuel to Low Enriched Uranium fuel (LEU). The new fuel MC5-485 consists of 

19,75% 235-U. At this stage several new MC elements have been inserted into the reactor core 

and are under a test procedure.

Prior to this test, thermal-hydraulic effects have been calculated by the operator using a 

specialized computer code called ‘SN’. The SN code is capable of performing thermal-hydraulic 

calculations of the fuel elements behaviour and has been verified and validated for the research 

reactor MARIA only.

The Polish National Atomic Energy Agency (PAA) has decided to try to cross-check the results 

of the analysis using the RELAP5 code although it is aware that the results of the analysis at 

this stage might need further elaboration and additional calculations. However an important aim 

is to gain experience in performing analysis using RELAP5 and to judge whether it is applicable 

and to what extent to the analysis of the research reactor.

The National Centre for Nuclear Research who is the operator of the research reactor MARIA 

has provided the results of two types of accidents: a Reactivity Initiated Accident (RIA) and Loss 

of Flow Accident (LOFA). The results of the analyses are part of a supplementary document1 to 

the Safety Analysis Report. The analysis of RIA was divided into four scenarios: two for reactor 

low power level operation (possible during start-up of the reactor or during work with low power 

level – 10 kW) and two for normal operation with maximum allowed power. Both cases were 

performed for slow and fast reactivity insertion. The SN code models the fuel element only. It 

does not include the possibility to model the whole reactor together with the safety systems. As 

a consequence of this limitation no analyses of the Loss Of Coolant Accident (LOCA) have been 

supplied as yet. Using RELAP should change this and enable the regulatory body to perform a 

LOCA analysis as well.

The Regulatory Body has cross checked the analyses made and presented by the operator in 

the supplementary document and has provided the comparison of results in this report. Due to 

other limitations of the SN code, the comparison is rather limited. Only a small number of 

parameters is included in the SN output. Thus, only those could be compared.

 1 Aneks 2012/1 do Eksploatacyjnego Raportu Bezpieczeństwa Reaktora MARIA Konwersja rdzenia reaktora MARIA 

na paliwo MC, July 2012.

2-1

2 FACILITY DESCRIPTION

2.1 MARIA research reactor technical information

The Maria research reactor is a pool type research reactor with 20-25 closed fuel channels in 

the core, with a beryllium moderator and graphite reflector. The designed maximum thermal 

power is 30 MW. The reactor is placed about 30 km from Warsaw in Świerk-Otwock and is 

operated by the National Centre for Nuclear Research (NCBJ). More technical information 

including a description of the primary safety systems is provided in Appendix A.

Figure 1. Simplified scheme of the Research Reactor ‘MARIA’ core configuration

.

Fuel channel

Beryllium plug

Hydraulic rabit

system

Control rod

Safety rod

PAR 

Berrylium block

Graphite plug
2-2

2.2 Fuel channel with fuel element technical information:

This report assumes that only the new type of fuel – the French LEU fuel MC5-485 with 19.75% 

of 235U is used. The fuel element is a pipe in pipe construction, consisting of 5 pipes with fuel 

(Fig.2 with numbers from 2 to 6) and filler. The fuel is a dispersion U3Si2-Al with AG3NE alloy 

as a clad material and SAW alloy (aluminium alloy type) as an outer tube of the fuel channel. 

Water in the fuel element flows through 6 gaps (numbered from 1 to 6 on the picture) and 

through a gap in the centre of the fuel element. Fuel elements work with various thermal power 

levels depending on the position in the core. Usually, fuel elements work in the centre of the 

core with thermal power at the level of about 1.2-1.6 MW and in the peripheral position of the 

core with power about 0.3-1.2 MW. The maximum allowed thermal power – the safety limit for 

this fuel is 1.8 MW and it is forbidden for the reactor to exceed the limit in any conditions.

Figure 2. Simplified scheme of the fuel channel with an MC fuel element

Fuel pipe nr

6 5 4 3 2 2 3 4 5 6 

6 5 4 3 2 1

Gap number

1 2 3 4 5 6 

Fuel channel ~ 3.5 m 

Fuel element ~ 1.3 m

Water

Fuel

Aluminum

AG3NE alloy

SAW alloy

A+

A+

0.079 m 
3-1

3 CODE INPUT AND MODEL DESCRIPTION

3.1 Nodalization

In order to cross-check the analysis it was necessary to prepare a model of the fuel channel 

with a fuel element consisting of 5 fuel pipes and a bypass in centre. The nodalization is 

presented on Fig.3. Water flowing in the channel is directed first to the outer part of channel 

(component 10), then split into three gaps between fuel pipes (components 20, 25 and 30). 

Next, the water mixes and changes direction of flow (in component 35, 40 and 45) and goes up 

through the rest of the gaps and bypass (components 50, 55, 60 and 80). Next, the water flows 

to the exit of the channel through the inner part of the channel (component 70).

Figure 3. Nodalization scheme of the MC fuel element. 

75 5

6 1

... ...

... ...

1 6

12 12 12 12 1 1 1

... ... 10 ... 10 ... 10 ... 10 ... 10 ...

... ... 1 ... 1 ... 1 ... 1 ... 1 ...

1 1 161 1 156 1 151 12 131 12 126 12

Passive heat structure

Active heat structure

Direction of the flow

70

60 160 55

65

80

45

180 155 150 130 25 125 20

15

10

50 30

35

40

110
3-2

3.2 Heat structures

Two types of heat structures - active and passive were used for modelling heat exchange. 

Passive heat structures without heat generation are used for modelling heat transfer between 

the outer and inner part of the fuel channel (node no. 110 on Figure 3), non-filled fuel pipe parts 

(161, 156, 151, 131, 126) and filler (180). Active heat structures are used for modelling fuel 

pipes with heat generation (160, 155, 150, 130, 125 consisting of 10 cells). Each cell in the 

active heat structure was divided into 17 meshes as is visualised on Figure 4. In case of passive 

structures each cell was divided into less than 10 meshes. 

Figure 4. Positioning of mesh points in each fuel pipe – grey colour clad material, red 

colour - fuel

For the purpose of this document it was required to check the temperature in four points:

External side of Clad on the Internal side of Pipe (ECIP) – mesh nr 1,

Internal side of Clad on the Internal side of Pipe (ICIP) – mesh nr 5,

Internal side of Clad on the External side of Pipe (ICEP) – mesh nr 13,

External side of Clad on the External side of Pipe (ECEP) – mesh nr 17.

The placement of the four points is shown on Figure 5.

Figure 5. Placement of measurement points

The heat generation distribution model was based on two factors: (1) heat generation in each 

0.6 mm

11 12 13 14 15 16

14 15 16

0.6 mm 0.8 mm

1 2 3 4 5 6 7 8 9 10

1 2 3 4 5 6 7 8 9 10 11 12 13 17

ECEP

ICIP ICEP

ECIP
3-3

pipe calculated by the computer code MCNP2 and (2) axial heat generation based on the cosine 

model with a slight shift downwards in order to simulate partial insertion of control rods into the 

core during operation.

Table 1. Distribution of heat generation on fuel pipes and comparison of heat generation 

with content of uranium

Pipe Heat generation 

[%]

Mass of U-235 [%]

2 11.0 11.15

3 14.1 15.58

4 18.1 20.00

5 23.8 24.43

6 33.0 28.84

3.3 Limitation of the model and errors

A model of the analysed objects, as well as data and calculations should always include an 

errors analysis that influence the final results. However the scenario analysed for the purpose of 

this document was made with conservative assumptions in the initial condition and did not 

include the influence of errors and sensitivity studies. The model used for this calculation was 

limited to a model of the fuel element only. Other elements of the reactor systems were not 

included. As a consequence it was necessary to: 

• omit influence of reactivity coefficients of the coolant in reactor pool and beryllium blocks 

positioned around the analysed fuel channel; the omitted thermal reactivity coefficients 

are positive but during postulated accidents, the increase of the temperature of the 

beryllium blocks and water of pool is very low,

• omit heat transfer between the fuel channel and water of the reactor pool; the influence 

of this factor is very small due to the very small difference in temperatures between 

water in the outer part of the fuel channel and the water in the pool (i.e. heated water 

flows in the internal part of fuel channel).

 2 Calculated by NCBJ in document: Aneks 2009/1 do Eksploatacyjnego Raportu Bezpieczeństwa Reaktora MARIA 

Badania paliwa MC

4-1

4 RESULTS

4.1 Steady state evaluation

Initial calculations were performed for steady-state conditions. The newly created model of the 

reactor with the new fuel elements for RELAP was used and compared with the results of 

steady state calculations received from the SN code. The limitations of the SN code do not allow 

to perform detailed comparisons, however peak cladding temperatures and heat flux were 

compared.

The steady state was calculated for the reactor normal operation deviated from full power.

Steady-state conditions

The conditions that were used in the simulation were chosen to simulate work of the fuel 

channel during normal operation with safety parameters equal to warning signals. In order to 

have such conditions the mass flow was reduced to 90% of nominal value and thermal power 

was increased to 110% of the nominal value.

Initial conditions:

• Cooling channel inlet water temperature Tin=318.15K 

• Mass flow Q=7.43kg/s (27m3

/h for density of water: 990kg/m3) (90% of nominal mass 

flow)

• Pressure at the fuel channel inlet p=1.7MPa

• Fuel channel pressure drop Δp=0.59MPa

• Fuel element thermal power 1.98MW (110% of nominal value)

Results

Temperature distribution on fuel pipes

The results of calculations are presented on the following figures – from Figure 6 to Figure 13. 
4-2

The temperature distribution on the internal side of the fuel pipe as below: 

Figure 6. Temperature distribution on ICIP of each fuel pipe

Figure 7. Temperature distribution on ECIP of each fuel pipe

-50

-40

-30

-20

-10

0

10

20

30

40

50

330 345 360 375 390 405 420 435

Core height [mm]

Temperature [K]

T6in

T5in

T4in

T3in

T2in

-50

-40

-30

-20

-10

0

10

20

30

40

50

330 345 360 375 390 405 420 435

Core height [mm]

Temperature [K]

T6ext

T5ext

T4ext

T3ext

T2ext
4-3

On the outer side of fuel pipe as below:

Figure 8. Temperature distribution on ICEP of each fuel pipe

Figure 9. Temperature distribution on ECEP of each fuel pipe

-50

-40

-30

-20

-10

0

10

20

30

40

50

330 345 360 375 390 405 420 435

Core height [mm]

Temperature [K]

T6in

T5in

T4in

T3in

T2in

-50

-40

-30

-20

-10

0

10

20

30

40

50

330 345 360 375 390 405 420 435

Core height [mm]

Temperature [K]

T6ext

T5ext

T4ext

T3ext

T2ext
4-4

Temperature distribution of water between pipes in gaps as below:

Figure 10. Water temperature distribution in gaps between fuel pipes. In – filler gap

Figure 11. Maximum temperature axial distribution in fuel pipe no. 6. Yellow dots –

calculation points in fuel pipe, red – fuel, blue – cladding

-50

-40

-30

-20

-10

0

10

20

30

40

50

320 335 350 365 380 395

Core height [mm]

Temperature [K]

T7

T6

T5

T4

T3

T2

In

420

425

430

435

440

445

450

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17

Temperature [K]

Calculations points placements[-] 
4-5

Heat flux distribution on outer side of fuel pipes

Figure 12. Heat flux distribution on inner side of fuel pipes.

Figure 13. Heat flux distribution on outer side of fuel pipes

-50

-40

-30

-20

-10

0

10

20

30

40

50

-0.75 -0.5 -0.25 0 0.25 0.5 0.75 1 1.25 1.5 1.75 2 2.25 2.5

Core height [mm]

Heat flux [MW/m2]

Q6in

Q5in

Q4in

Q3in

Q2in

-50

-40

-30

-20

-10

0

10

20

30

40

50

0 0.25 0.5 0.75 1 1.25 1.5 1.75 2 2.25 2.5 2.75

Core height [mm]

Heat flux [MW/m2]

Q6ex

t

Q5ex

t

Q4ex

t
4-6

Comparison of results

A comparison of two calculations is presented in Table 2. The main results of the RELAP5 

calculations with inlet temperature Tin=318.15K presented in the chapter above are compared 

with the results received using the SN code. Additionally one more calculation using RELAP5 

was performed for the same conditions except for the inlet temperature which was changed to 

Tin=323.15K

Table 2. Comparison of results for two scenarios

RELAP5 RELAP5 

(Tin=323.1K) SN

Maximum peak clad temperature 

on ECIP of fuel pipe [K] 427.6 431.0 425.6

Maximum peak coolant 

temperature [K] 390.9 396.2 no data

Maximum heat flux [MW/m2] 2.67 2.68 2.63

Maximum temperature in the fuel 

centre point [K] 446.6 450.0 no data

4.2 LOFA - Loss of flow in the fuel channel cooling system

Accident conditions

Loss of flow in the fuel channel cooling system is possible in case of the loss of power in the 

pump system. As a result a sudden decrease of pressure occurs in the cooling channel that 

leads to the initiation of the emergency signal and shutdown of the reactor. Furthermore, after 

the loss of flow a rapid increase of fuel clad temperature and cooling temperature in gaps 

between fuel pipes occurs. According to the scenario a few seconds after the loss of power in 

the pump system, the work of a backup pump should be initiated with the power supply from 

accumulator batteries and with lower speed – 1500 r/s. After the reactor shutdown and before 

the flow is stabilized another small temperature jump can be detected. 

Initial and boundary conditions:

Initial conditions:

• Cooling channel Inlet water temperature Tin=318.15K

• Mass flow Q=8.25kg/s (30m3

/h for density of water:990kg/m3)

• Pressure at the fuel channel inlet pin=1.7MPa

• Fuel channel pressure drop Δp=0.59MPa

• Fuel element thermal power 1.8MW

Boundary conditions:

• Alarm signal – signal from decrease pressure to 1.4MPa

• Signal delay time t1=0.2s

• Effective time of safety and control rods insertion t2=0.15s

• Inserted negative reactivity (from rods PK and PB) ρ=-5.5$ (-2$ PK, -3.5$ PB – with the 
4-7

assumption that the rod with the highest weight failed)

• Loos of flow modelled as in the Supplement3

• Temperature reactivity coefficients: αf=-0.25ȼ/deg, αw=-2.02ȼ/deg

Results

The sequence of events:

Table 3. Sequence of events for LOFA

Time [s]

0.00 Pump trip, loos of flow

0.40 Alarm signal p=1.4Mpa

0.75 Beginning of the negative reactivity insertion from PK and PB

0.78 Peak Clad Temperature on ICIP of fuel pipe nr 6 - 440.38 K 

0.79 Peak Clad Temperature on ECIP of fuel pipe nr 6 - 432.07 K

0.89 Peak Coolant Temperature in the gap between fuel pipe nr 3 and nr 4 – 394.07 

K

6.32 Second Peak Clad Temperature on ECIP of fuel pipe nr 6 with 2 cooling 

pumps – 381.56 K

13.90 Second Peak Clad Temperature on ECIP of fuel pipe nr 6 with 1 cooling pump 

– 399 K

Table 4. Distribution of calculated top temperatures on fuel pipes

Pipe nr 2 3 4 5 6

RELAP5 

component

160 155 150 130 125

Side of pipe In. Out. In. Out. In. Out. In. Out. In. Out.

Max. temperature 

on the outer layer 

of clad

413 415 413 413 416 418 426 426 432 430

Max. temperature 

on the inner layer 

of clad

421 422 420 420 423 424 433 433 440 439

 3 Aneks 2012/1 do Eksploatacyjnego Raportu Bezpieczeństwa Reaktora MARIA Konwersja rdzenia reaktora MARIA 

na paliwo MC, July 2012.
4-8

Comparison of results

Clad temperature

The highest outer clad temperature calculated with the SN code was 433.4K, and temperature 

calculated with RELAP5 code was 432K (outer layer temperature – 440K). Both codes 

calculated the highest temperature in the same place – on the internal side of pipe no 6. 

Figure 14. Cladding and water temperature changes. SN code: water and fuel element 

outlet temperature, RELAP5: water I – fuel element outlet temperature, water II 

- fuel channel outlet temperature

Figure 15. Cladding and water temperature changes. SN code: water and fuel element 

outlet temperature, RELAP5: water I – fuel element outlet temperature, water II 

- fuel channel outlet temperature. Wider scale range.

340

350

360

370

380

390

400

410

420

430

440

0 1 2 3 4 5 6 7 8 9 10

Temperature [K]

Time [s]

SN - cladding

SN - water

RELAP5 - cladding

RELAP5 - water I

RELAP5 - water II

340

350

360

370

380

390

400

410

420

430

440

0 5 10 15 20 25 30 35 40 45 50 55 60

Temperature [K]

Time [s]

SN - cladding

SN - water

RELAP5 - cladding

RELAP5 - water I

RELAP5 - water II
4-9

ONBR4 parameter

Figure 16. ONBR parameter changes

 

4 ONBR (Onset of Nuclear Boiling Ratio) should be greater than 1.2, where:

ONBR=(TONB-Tin)/(Twall-Tin)

TONB=Tsat+0.182*q0.35/p0.23 (Forester-Greif correlations)

Tin - inlet coolant temperature, 

Twall - the clad surface temperature, 

Tsat - saturation coolant temperature, 

q - heat flux [W/m2

], 

p - pressure [bar].

0

0.5

1

1.5

2

2.5

3

3.5

4

4.5

5

5.5

0 5 10 15 20 25 30 35 40 45 50 55 60

ONBR [C]

Time [s]

SN

RELAP5
4-10

Second clad temperature maximum (depending on the number of cooling pumps)

Table 5. Comparison of results for second temperature peak

Parameter

SN RELAP5

1 pump 2 pumps 1 pump 2 pumps

Maximum outer 

temperature of 

clad [K]

387.25 364.98 399.0 381.56

Minimum ONBR 1.74 2.60 1.84 2.34

Differences in results

Differences in the results calculated by RELAP5 and the SN code arose due to many factors 

and not necessarily related only to nodalization. One of the factors - is a different flow model. In 

case of the SN code a more pessimistic method was used – coolant flow from fuel channel 

occurs at the same time in all gaps between fuel pipes. In case of RELAP5 a more realistic 

model was used. The water first flows down into the three gaps then gets mixed and next fills 

the rest of the gaps between the fuel pipes. The second example of differences is another 

model of decay heat. In case of RELAP5 decay heat was calculated by the code from kinetics 

and time of operation, whereas in the case of the SN code - decay heat was calculated on the 

basis of the old type of fuel measurements.

4.3 Slow reactivity insertion accident on low power level

Accident conditions

In case when the operator undertakes incorrect actions or a malfunction of the reactivity 

regulation system occurs, it is possible that as a result, positive reactivity is inserted into the 

core with the maximum reactivity speed 0.04$/s. This scenario was checked for low power level 

conditions.

Initial conditions:

• Cooling channel Inlet water temperature Tin=313.15K

• Mass flow Q=8.268kg/s (30m3

/h for density of water: 992.2kg/m3)

• Pressure at the fuel channel inlet pin=1.7MPa

• Fuel channel pressure drop Δp=0.59MPa

• Fuel element thermal power 10kW

Boundary conditions:

• Alarm signal – signal from increase of power to 480% - in this case to 48kW

• Signal delay time t1=0.2s

• Effective time of safety and control rods insertion t2=0.15s

• Insertion positive reactivity from accident t=0s ρ=0.04$/s, ρmax=1.5$
4-11

• Inserted negative reactivity (from rods PK and PB)ρ=-5.5$ (-2$ PK, -3.5$ PB)

• Temperature reactivity coefficients: αf=-0.23ȼ/deg, αw=-1.93ȼ/deg

Comparison of results

Table 6. Comparison of results for SRIA on low power level

Sequence of events

SN RELAP5

Time [s] Value Time [s] Value

Start of positive reactivity 

insertion 0.0 - 0.0 -

Alarm signal 480% of power 12.3 - 12.48 -

Start of negative reactivity 

insertion no data - 12.83 -

Maximum power 12.7 53kW 12.83 52.7kW

Maximum peak cladding 

temperature on ECIP of fuel 

pipe nr 6

no data 316.15K 12.85 316.14K

Maximum peak cladding 

temperature on ICIP of fuel 

pipe nr 6

no data no data 12.85 316.44K

Minimum ONBR no data about 50 12.85 53.8

Maximum peak coolant 

temperature in gap nr 3 

between fuel pipe nr 3 and 4

no data no data 12.9 314.72K

This scenario has the lowest impact on the fuel elements. The temperature peaks of water and 

clad are very small - smaller than fluctuations of temperature during normal operation of the 

reactor. 
4-12

Figure 17. Reactivity changes. RELAP5: total reactivity change; water and fuel: reactivity 

change due to coolant and fuel temperature reactivity coefficients

Figure 18. Power changes of fuel element for SRIA on low power level

-500

-400

-300

-200

-100

0

100

0 3 6 9 12 15

Reactivity[c]

Time [s]

RELAP5 - change of

reactivity

0

10

20

30

40

50

60

0 3 6 9 12 15

Power [kW]

Time [s]

RELAP5
4-13

4.4 Fast reactivity insertion accident on low power level

One of the important scenarios addressed in the supplementary document is the fast inflow of 

cold water into the core resulting in a sudden increase of reactivity. The negative reactivity 

coefficients lead to the increase of power in the fuel elements. The cold water is directed first 

between the first three pipes – pipes no. 4, 5, 6 on Figure 2 and after about 0.2s into the rest of 

the gaps. 

Accident conditions

Initial conditions:

• Cooling channel Inlet water temperature Tin=323.15K, after 1s insertion of cold water 

T2in=283.15K

• Mass flow Q=8.268kg/s (30m3

/h for density of water: 992.2kg/m3) T2in=283.15K.

• Pressure at the fuel channel inlet pin=1.7MPa

• Fuel channel pressure drop Δp=0.59MPa

• Fuel element thermal power 10kW

Boundary conditions:

• Alarm signal – increase of power to 480% - in this case to 48kW

• Signal delay time t1=0.2s

• Effective time of safety and control rods insertion t2=0.15s

• Insertion of positive reactivity from accident t=0s ρ=0.04$/s, ρmax=1.5$

• Insertion of negative reactivity (from rods PK and PB) ρ=-5.5$ (-2$ PK, -3.5$ PB)

• Temperature reactivity coefficients: αf=-0.23ȼ/deg, αw=-1.93ȼ/deg

Comparison of results

Table 7. Comparison of results for FRIA on low power level

Sequence of events:

SN RELAP5

Time [s] Value Time [s] Value

Start of insertion of cold water to the 

fuel channel 1.0 - 1.0 -

Minimum ONBR no data about 5 1.34 4.95

Cold water In fuel pipes zone 1.59 - 1.67 -

Alarm 480% of power 2.44 - 2.47 -

Start of negative reactivity insertion 2.79 - 2.82 -

Maximum power 2.83 96.3kW 2.85 80.9kW
4-14

Figure 19. Power changes of fuel element for FRIA on low power level

Figure 20. ONBR parameter changes

0

10

20

30

40

50

60

70

80

90

0 1 2 3 4 5

Power [kW]

Time [s]

RELAP5

1

10

100

1000

0 1 2 3 4 5

ONBR [-]

Time [s]

RELAP5
4-15

Figure 21. Reactivity changes - RELAP5 calculations: i) change of reactivity: total reactivity change, ii) water: change due to coolant temperature reactivity 

coefficients, iii) fuel: change due to fuel temperature reactivity coefficient

4.5 Slow reactivity insertion accident during normal operation of reactor 

Accident conditions

The scenario analyzed in this transient is very similar to the slow reactivity insertion on low 

power. The main difference is that the reactor is in the normal operation mode, on full power, 

with the maximum allowed thermal power generation. In case when the operator undertakes 

incorrect actions or a malfunction of the reactivity regulation system occurs, it is possible that as 

a result, positive reactivity is inserted into the core with the maximum reactivity speed 0.04$/s. 

Initial conditions:

• Cooling channel Inlet water temperature Tin=318.15K, 

• Mass flow Q=8.252kg/s (30m3

/h for density of water: 990.2kg/m3)

• Pressure at the fuel channel inlet pin=1.7MPa

• Fuel channel pressure drop Δp=0.59MPa

• Fuel element thermal power 1.8MW

Boundary conditions:

-500

-400

-300

-200

-100

0

100

0 1 2 3 4 5

Reactivity [c]

Time [s]

RELAP5 - change of reactivity

RELAP5 - water

RELAP5 - fuel
4-16

• Alarm signal – signal from increase of power to 120% - in this case to 2.16MW

• Signal delayed t1=0.2s

• Effective time of safety and control rods insertion t2=0.15s

• Insertion of positive reactivity from accident t=0s ρ=0.04$/s, ρmax=1.5$

• Insertion of negative reactivity (from rods PK and PB) ρ=-5.5$ (-2$ PK, -3.5$ PB)

• Temperature reactivity coefficients: αf=-0.23ȼ/deg, αw=-1.93ȼ/deg

Comparison of results

Table 8. Comparison of results for SRIA during normal operation

Sequence of events:

SN RELAP5

Time [s] Value Time [s] Value

Start of insertion of positive 

reactivity 0.0 0.04$/s 0.0 0.04$/s

Alarm signal – power 120% 5.37 - 6.44 -

Start of insertion of negative 

reactivity no data - 6.79 -

Maximum power 5.72 2.189MW 6.80 2.183MW

Maximum peak cladding 

temperature on ECIP of fuel 

pipe nr 6

5.73 424.86K 6.80 428.16K

Maximum peak cladding 

temperature on ICIP of fuel 

pipe nr 6

no data - 6.80 440.5K

Minimum ONBR 5.73 about 1.6 6.80 1.60

Maximum peak coolant 

temperature on exit from fuel 

element

5.77 381.29K 6.86 386K
4-17

Figure 22. Power changes of fuel element for SRIA on nominal power level

Figure 23. Cladding and water temperature changes. RELAP5 and SN codes: cladding –

cladding temperature, water – fuel element outlet temperature

0

0.5

1

1.5

2

2.5

0 1 2 3 4 5 6 7 8 9 10

Power [MW]

Time [s]

SN

RELAP5

320

340

360

380

400

420

440

0 1 2 3 4 5 6 7 8 9 10

Temperature [K]

Time [s]

SN -cladding

SN - water

RELAP5 - cladding

RELAP5 - water
4-18

Figure 24. ONBR parameter changes

Figure 25. Reactivity changes. RELAP5 and SN codes: change of reactivity - total reactivity change, water - change due to coolant temperature reactivity 

coefficients, fuel - change due to fuel temperature reactivity coefficients 

0

2

4

6

8

10

12

14

16

0 2 4 6 8 10

ONBR [-]

Time [s]

SN

RELAP5

-500

-400

-300

-200

-100

0

100

0 2 4 6 8 10

Reactivity [c]

Time [s]

SN - change of reactivity

SN - water

SN - fuel

RELAP5 - change of reactivity

RELAP5 - water

RELAP5 - fuel
4-19

4.6 Fast reactivity insertion accident during reactor normal operation

Accident Conditions

A break of control rods is another scenario included in the supplementary document. The break 

of control rods leads to fast insertion of positive reactivity into the reactor. It is assumed that the 

maximum insertion of positive reactivity is equal to 1.5$ with the top speed of insertion 4$/s.

Initial conditions:

• Cooling channel inlet water temperature Tin=318.15K, 

• Mass flow Q=8.252kg/s (30m3

/h for density of water: 990.2kg/m3)

• Pressure at the fuel channel inlet pin=1.7MPa

• Fuel channel pressure drop Δp=0.59MPa

• Fuel element thermal power 1.8MW

Boundary conditions:

• Alarm signal – increase of power to 120% - in this case to 2.16MW

• Signal delay time t1=0.2s

• Effective time of safety and control rods insertion t2=0.15s

• Insertion of positive reactivity from accident t=0s ρ=0.04$/s, ρmax=1.5$

• Insertion of negative reactivity (from rods PK and PB) ρ=-5.5$ (-2$ PK, -3.5$ PB)

• Temperature reactivity coefficients: αf=-0.23ȼ/deg, αw=-1.93ȼ/deg

Comparison of results

Table 9. Comparison results for FRIA during normal operation

Sequence of events:

SN RELAP5

Time [s] Value Time [s] Value

Start of 0.0 4$/s 0.0 4$/s

Alarm signal 120% 0.08 - 0.07 -

Maximum thermal power 0.40 8.6MW 0.38 5.62MW

Maximum peak cladding 

temperature on ECIP of fuel 

pipe nr 6

no data 598.88K 0.40 515.52K

Maximum peak cladding 

temperature on ICIP of fuel 

pipe no. 6 

no data - 0.40 547.46K

Minimum ONBR 0.45 0.64 0.41 0.928

Start of insertion of negative 

reactivity 0.44 - 0.42 -

Max. peak coolant temperature 

on exit from fuel element 0.58 460.65K 0.55 448.39K
4-20

The main differences in the results between RELAP and the SN code are due to the different 

models of reactor kinetics. RELAP5 uses the point kinetic model and this model was applied to 

the RIA analysis. In the nodalization model applied, total reactivity was divided into many 

sections depending on the position in the fuel pipes or in the gap between pipes. The fuel 

reactivity coefficient was divided in 50 point, 10 points in each cell of the fuel pipe because the 

values of the divided fuel reactivity coefficients depend on the distribution of heat generation on 

fuel pipes and axial distribution of heat generation (i.e. shifted cosine model). The coolant 

reactivity coefficient was divided into 60 points, 10 points in each gap. The values of the divided 

coolant reactivity coefficient depend on the distribution of the mass flow between gaps and the 

distribution of heat (shifted cosine model). In case of the SN code a more pessimistic model was 

used.

Figure 26. Power changes of fuel element for FRIA on nominal power level

0

1

2

3

4

5

6

7

8

9

0 0.5 1 1.5 2 2.5 3

Power [MW]

Time [s]

SN

RELAP5
4-21

Figure 27. ONBR parameter changes

Figure 28. Cladding and water temperature changes. RELAP5 and SN codes: cladding –

cladding temperature, water I – fuel element outlet temperature, water II - fuel 

channel outlet temperature

0

1

2

3

4

5

6

7

8

9

0 0.5 1 1.5 2 2.5 3

ONBR [-]

Time [s]

RELAP5

SN

320

370

420

470

520

570

620

0 0.5 1 1.5 2 2.5 3

Temperature[K]

Time [s]

SN - cladding

SN - water I

RELAP5 - cladding

RELAP5 - water I

RELAP5 - water II
4-22

Figure 29. Reactivity changes. RELAP5 and SN codes: change of reactivity - total 

reactivity change, water - change due to coolant temperature reactivity 

coefficients, fuel - change due to fuel temperature reactivity coefficients

-400

-300

-200

-100

0

100

0 0.5 1 1.5 2 2.5 3

Reactivity[c]

Time [s]

SN - change of reactivity

SN - water

SN - fuel

RELAP5 - change of reactivity

RELAP5 - water

RELAP5 - fuel
5-1

5 RUN STATISTICS

All analysis were performed on one computer:

Intel(R) Core(TM) i3-2125 CPU @ 3.30 GHz

RAM memory :4.00 GB

Windows 7 Professional – SP1, 64-bit version

IFC (Intel Fortran Compiler) for RELAP5 

Figure 30. Calculation time for various cases

6-1

6 CONCLUSIONS

Most of the results of the simulation for the research reactor MARIA made with RELAP5 code 

showed that there is no big difference between the results achieved by the validated SN and the 

RELAP5 codes. Only in one case (RIA with fast reactivity insertion with maximum power level) 

there is the opportunity to exceed the lowest allowed level of the ONBR parameter. Exceeding 

this parameter can cause the onset of boiling of the coolant in the gap between the fuel pipes. In 

the analysed case, the duration of time when ONBR is lower than 1.2 is very short (about 0.35s) 

and should not cause any damage to the fuel and clad material. In the fast RIA scenario, the 

power jump during the insertion of positive reactivity was stopped by the negative reactivity 

coefficients (fuel and coolant) before insertion of the safety and control rods into the core could 

be initiated. 

In other simulated scenarios, no opportunity to exceed the ONBR parameter or temperature 

limit of clad – 452K occurred. 

In the analysed LOFA scenario, the calculations showed that enough cooling capability is 

provided even when only one pump is working with a lower rotation speed than the normally 

required two pumps. 

The content of this report does not cover all possible accident conditions that should be 

analysed for the research reactor. Further analysis will be necessary. A comparison of the SN 

and RELAP5 codes showed that RELAP5 can be used in the safety analysis for the research 

reactor MARIA.

7-1

7 REFERENCES 

1. “Aneks 2009/1 do Eksploatacyjnego Raportu Bezpieczeństwa Reaktora MARIA Badania 

paliwa MC”, 2009 (in Polish). 

2. “Aneks 2012/1 do Eksploatacyjnego Raportu Bezpieczeństwa Reaktora MARIA 

Konwersja rdzenia reaktora MARIA na paliwo MC”, July 2012 (in Polish).

3. (SAR) “Eksploatacyjny Raport Bezpieczeństwa Reaktora MARIA”, 2009 (in Polish). 

A - 1

APPENDIX A – TECHNICAL INFORMATION ON THE RESEARCH 

REACTOR MARIA

The research reactor ‘Maria’ was designed by the Institute for Nuclear Studies in Poland and is 

operated by the National Centre for Nuclear Research that was created on the basis of two 

older Institutes. The reactor started to work in 1974 and is under operation till now except for the 

period of 1986 to 1991 when it was undergoing modernization. 

It is a pool type reactor with closed fuel channels and closed fuel channel primary cooling circuit, 

primary pool cooling circuit and secondary cooling circuit. The fuel channel cooling circuit 

includes also a pressurizer. 

At present the reactor is used for the production of isotopes and for performing experiments. 

The total thermal power is 30 MW. More data that might be of interest is presented below.

Thermo-hydraulic 

parameters

During a typical cycle of work:

Thermal power of a fuel channel: 15-19 MW(th) for 19-23 

fuel channels,

Inlet temperature to fuel channels: 303-323 K,

Temperature increase in the core: 20-30 deg,

Hot leg pressure (in outlet collector): about 0.9-1 MPa,

Cold leg pressure (in inlet collector): about 1.7-1.8 MPa,

Minimum flow in fuel channels 30 m3/h for channels with 

maximum thermal power 1.8 MW, 

Minimum flow is 15 m3/h for channels with 0.9 MW (in 

peripheral core position).

Pressurizer Filled with water and helium gas under high pressure

At pressure about 1.7 MPa maintains sufficient water 

inventory in the circuit. 

Safety signals 

causing reactor 

scram

1) Decrease of mass flow in the fuel channel in the channel 

cooling circuit. Each fuel channel is equipped with 

temperature and mass flow measurements (it is important 

for calculating the thermal power of the element), a small 

value of the mass flow in the channel will generate a “low 

mass flow” signal i.e. a warning signal when the flow 

drops to 90% of nominal mass flow and an alarm when 

the flow drops to 80% of nominal mass flow.

2) Kinetics control system. In case of sudden power jump 

signal is generated through detectors and other systems. 

It’s warning signal when is 110% of nominal reactor 

power, and alarm signal in case of 120% of nominal 

power. Additional safety signal for fast reactivity jump it is 
A - 2

alarm signal from increase of period of the reactor.

Reactivity coefficients Fuel reactivity coefficient (negative) -0.23¢/deg to -0.25¢/deg

Coolant reactivity coefficient in the fuel channel (negative) 

-1.93¢/deg to -2.09¢/deg

Coolant reactivity coefficient of the pool plus moderator 

reactivity coefficient (positive) +1.9¢/deg

Void reactivity coefficient (negative) -9.37 ¢/% of void to -

9.71¢/% of void

Values of coefficients depend on the beginning or end of the 

fuel cycle and number of molybdenum channels in the core 

(none, one or two molybdenum channels).

Control system The reactor power is controlled through changes of position 

of the control rods and automatic or manual changes of 

position of the UAR. The UAR is an automatic regulation 

system, that through the change of position of one control 

rod in the reactor core controls the power level and 

maintains, if it’s necessary, the criticality of the reactor. 

Shutdown system The shutdown system is provided through safety rods 

(insertion reactivity from -7.5$ to -11$ to the core) and 

control rods (the weights depend on the position of the rods 

in the core, it can be pessimistically assumed that the 

injection is -2.5$). Safety rods and control rods work in 

accordance to the fail-safe rule. In case of loss of the power 

supply the safety rods will be automatically released from 

electromagnets into the reactor core.

It’s also possible to remove two fuel elements from the core. 

This is done by moving two fuel type elements (REP). This 

action is slower than the movement of safety rods. 

Sometimes it’s impossible to remove the REP because of 

temperature stress until several hours after reactor 

shutdown. The reactivity of two REPs is about 4.2+/-0.5$.

The shutdown system does not depend on the boron 

injection system.

Emergency core 

cooling system

In case of low water level in the pressurizer, an additional 

pump (1u6) that is connected to the pressurizer is 

automatically switched on and pumps water from the tank 

system (water volume 20-30m3) into the pressurizer. The 

solution is good only in case of a small leakage from the 

channel cooling circuit. 

The gas discharge system from the pressurizer. In case of 

very low water level in the pressurizer a discharge of helium 
A - 3

into the tank system through a system of valves will take 

place. This will result in a sudden depressurization of the 

channel cooling circuit.

The safety vales 1z100A/B. In case of depressurization the 

valves automatically open and connect the channel cooling 

circuit with pool of the reactor (due to the pressure difference 

between two circuits).

Fuelling Fuelling is performed when necessary depending on the 

reactivity supply, however always before a new work cycle. 

Refuelling, minimum 48 hours after a previous cycle, 

includes also a possibility of adding fuel elements removed 

after earlier cycles.

Cooling system Fuel cooling channels are cooled by two from four pumps. 

After shut-down is done by two from the four mentioned 

pumps but with rotation speed changed from 3000r/s to 

1500r/s. Hot water from the core passes through the heat 

exchangers system (four from six) transferring heat to the 

secondary circuit.

The pool is individually cooled by three from four pumps and 

in shutdown mode - by one from two shutdown pumps.

There is one secondary cooling circuit for the fuel cooling 

circuit and the pool cooling circuit. It pumps water to the 

outer cooling tower with ventilators. During normal operation 

two from three pumps and after shutdown one from three 

shutdown pumps are in operation. 

During loss of external power after a rapid shutdown, in 

order to remove decay heat, about 4 hours of cooling with 

post-shutdown pumps is necessary. The post-shutdown 

pumps are powered by accumulator batteries or diesel 

generators.

Moderator Beryllium blocks are used as a moderator. They are placed 

between fuel channels.

Reflector Graphite blocks are used as a reflector. They placed around 

beryllium blocks and fuel channels.

Operation The reactor works in cycles lasting from five to ten days with 

nominal power usually between 16 and 23 MW(th). In some 

cases the reactor is used for training of students and then it 

operates for several hours with the power level about 10 

kW(th).

Applications Production of radioactive materials for medicine – mainly 
A - 4

molybdenum production in special molybdenum channels.

Training of students.

Research activities.

Safety analysis Safety Analysis Report [1] updated in 2009. 

Update of the report is planned till 03.2015.
B - 1

APPENDIX B – INPUT FILE. 

RESEARCH REACTOR ‘MARIA’

STEADY STATE CALCULATIONS INPUT

DATE: 26.10.2012
B - 2

=MARIA

*m: SNAP:Symbolic Nuclear Analysis Package, Version 2.2.0, 

September 04, 2012

*m: PLUGIN:RELAP Version 4.3.0

*m: CODE:RELAP5 Version 3.3

*m: DATE:10/26/12

****************************** Model Options 

****************************** type state

100 new transnt

* iunits ounits

102 si si

* tend minstep maxstep copt pfreq majed rsrtf

201 10.0 1.0e-8 0.5 3 5 100 1000

20500000 9999

******************************* Control Blocks 

******************************* name type scale ival iflag limit

20500010 "dP_15-65" sum 1.0 5.882538e5 0 0

* a0 scale name param

20500011 0.0 1.0 p 15010000

20500012 -1.0 p 65010000

* name type scale ival iflag limit

20500020 "dT_10-70" sum 1.0 0.38535583 0 0

* a0 scale name param

20500021 0.0 -1.0 tempf 10010000

20500022 1.0 tempf 70060000

* name type scale ival iflag limit

20500030 "Ent_70" mult 1.0 1.743369e6 0 0

* input param input param

20500031 hvmix 70060000 mflowj 74000000

* name type scale ival iflag limit

20500040 "Power" sum 1.0 8973.1709 0 0

* a0 scale name param

20500041 0.0 -1.0 cntrlvar 5

20500042 1.0 cntrlvar 3

* name type scale ival iflag limit

20500050 "Ent_10" mult 1.0 1.734396e6 0 0

* input param input param

20500051 hvmix 10010000 mflowj 6000000

* name type scale ival iflag limit

20500100 "unnamed" sum 1.0 323.40231 0 0

* a0 scale name param

20500101 0.0 1.0 httemp 6000113

* name type scale ival iflag limit

20500110 "unnamed" sum 1.0 323.46774 0 0

* a0 scale name param

20500111 0.0 1.0 httemp 6000213

* name type scale ival iflag limit

20500120 "unnamed" sum 1.0 323.52133 0 0

* a0 scale name param

20500121 0.0 1.0 httemp 6000313

* name type scale ival iflag limit

20500130 "unnamed" sum 1.0 323.55933 0 0

* a0 scale name param

20500131 0.0 1.0 httemp 6000413

* name type scale ival iflag limit

20500140 "unnamed" sum 1.0 323.57919 0 0

* a0 scale name param

20500141 0.0 1.0 httemp 6000513

* name type scale ival iflag limit

20500150 "unnamed" sum 1.0 323.57993 0 0

* a0 scale name param

20500151 0.0 1.0 httemp 6000613

* name type scale ival iflag limit

20500160 "unnamed" sum 1.0 323.56198 0 0

* a0 scale name param

20500161 0.0 1.0 httemp 6000713

* name type scale ival iflag limit

20500170 "unnamed" sum 1.0 323.5274 0 0

* a0 scale name param

20500171 0.0 1.0 httemp 6000813

* name type scale ival iflag limit

20500180 "unnamed" sum 1.0 323.47955 0 0

* a0 scale name param

20500181 0.0 1.0 httemp 6000913

* name type scale ival iflag limit

20500190 "unnamed" sum 1.0 323.45679 0 0

* a0 scale name param

20500191 0.0 1.0 httemp 6001013

* name type scale ival iflag limit

20500200 "unnamed" sum 1.0 323.40326 0 0

* a0 scale name param

20500201 0.0 1.0 httemp 6000105

* name type scale ival iflag limit

20500210 "unnamed" sum 1.0 323.46854 0 0

* a0 scale name param

20500211 0.0 1.0 httemp 6000205

* name type scale ival iflag limit

20500220 "unnamed" sum 1.0 323.5217 0 0

* a0 scale name param

20500221 0.0 1.0 httemp 6000305

* name type scale ival iflag limit

20500230 "unnamed" sum 1.0 323.55899 0 0

* a0 scale name param

20500231 0.0 1.0 httemp 6000405

* name type scale ival iflag limit

20500240 "unnamed" sum 1.0 323.57797 0 0

* a0 scale name param

20500241 0.0 1.0 httemp 6000505

* name type scale ival iflag limit

20500250 "unnamed" sum 1.0 323.57767 0 0

* a0 scale name param

20500251 0.0 1.0 httemp 6000605

* name type scale ival iflag limit

20500260 "unnamed" sum 1.0 323.55865 0 0

* a0 scale name param

20500261 0.0 1.0 httemp 6000705

* name type scale ival iflag limit

20500270 "unnamed" sum 1.0 323.52307 0 0

* a0 scale name param

20500271 0.0 1.0 httemp 6000805

* name type scale ival iflag limit

20500280 "unnamed" sum 1.0 323.47437 0 0

* a0 scale name param

20500281 0.0 1.0 httemp 6000905

* name type scale ival iflag limit

20500290 "unnamed" sum 1.0 323.45117 0 0

* a0 scale name param

20500291 0.0 1.0 httemp 6001005

* name type scale ival iflag limit

20500300 "unnamed" sum 1.0 323.42294 0 0

* a0 scale name param

20500301 0.0 1.0 httemp 5500113

* name type scale ival iflag limit

20500310 "unnamed" sum 1.0 323.49878 0 0

* a0 scale name param

20500311 0.0 1.0 httemp 5500213

* name type scale ival iflag limit

20500320 "unnamed" sum 1.0 323.56104 0 0

* a0 scale name param

20500321 0.0 1.0 httemp 5500313

* name type scale ival iflag limit

20500330 "unnamed" sum 1.0 323.60513 0 0

* a0 scale name param

20500331 0.0 1.0 httemp 5500413

* name type scale ival iflag limit

20500340 "unnamed" sum 1.0 323.62796 0 0

* a0 scale name param

20500341 0.0 1.0 httemp 5500513

* name type scale ival iflag limit

20500350 "unnamed" sum 1.0 323.62811 0 0

* a0 scale name param

20500351 0.0 1.0 httemp 5500613

* name type scale ival iflag limit

20500360 "unnamed" sum 1.0 323.60602 0 0

* a0 scale name param

20500361 0.0 1.0 httemp 5500713

* name type scale ival iflag limit

20500370 "unnamed" sum 1.0 323.5639 0 0

* a0 scale name param

20500371 0.0 1.0 httemp 5500813

* name type scale ival iflag limit

20500380 "unnamed" sum 1.0 323.50562 0 0

* a0 scale name param

20500381 0.0 1.0 httemp 5500913

* name type scale ival iflag limit
B - 3

20500390 "unnamed" sum 1.0 323.47556 0 0

* a0 scale name param

20500391 0.0 1.0 httemp 5501013

* name type scale ival iflag limit

20500400 "unnamed" sum 1.0 323.43329 0 0

* a0 scale name param

20500401 0.0 1.0 httemp 5500105

* name type scale ival iflag limit

20500410 "unnamed" sum 1.0 323.51294 0 0

* a0 scale name param

20500411 0.0 1.0 httemp 5500205

* name type scale ival iflag limit

20500420 "unnamed" sum 1.0 323.57779 0 0

* a0 scale name param

20500421 0.0 1.0 httemp 5500305

* name type scale ival iflag limit

20500430 "unnamed" sum 1.0 323.62311 0 0

* a0 scale name param

20500431 0.0 1.0 httemp 5500405

* name type scale ival iflag limit

20500440 "unnamed" sum 1.0 323.64563 0 0

* a0 scale name param

20500441 0.0 1.0 httemp 5500505

* name type scale ival iflag limit

20500450 "unnamed" sum 1.0 323.64407 0 0

* a0 scale name param

20500451 0.0 1.0 httemp 5500605

* name type scale ival iflag limit

20500460 "unnamed" sum 1.0 323.61902 0 0

* a0 scale name param

20500461 0.0 1.0 httemp 5500705

* name type scale ival iflag limit

20500470 "unnamed" sum 1.0 323.57294 0 0

* a0 scale name param

20500471 0.0 1.0 httemp 5500805

* name type scale ival iflag limit

20500480 "unnamed" sum 1.0 323.51001 0 0

* a0 scale name param

20500481 0.0 1.0 httemp 5500905

* name type scale ival iflag limit

20500490 "unnamed" sum 1.0 323.47787 0 0

* a0 scale name param

20500491 0.0 1.0 httemp 5501005

* name type scale ival iflag limit

20500500 "unnamed" sum 1.0 323.45538 0 0

* a0 scale name param

20500501 0.0 1.0 httemp 5000113

* name type scale ival iflag limit

20500510 "unnamed" sum 1.0 323.52072 0 0

* a0 scale name param

20500511 0.0 1.0 httemp 5000213

* name type scale ival iflag limit

20500520 "unnamed" sum 1.0 323.56552 0 0

* a0 scale name param

20500521 0.0 1.0 httemp 5000313

* name type scale ival iflag limit

20500530 "unnamed" sum 1.0 323.58615 0 0

* a0 scale name param

20500531 0.0 1.0 httemp 5000413

* name type scale ival iflag limit

20500540 "unnamed" sum 1.0 323.58093 0 0

* a0 scale name param

20500541 0.0 1.0 httemp 5000513

* name type scale ival iflag limit

20500550 "unnamed" sum 1.0 323.55032 0 0

* a0 scale name param

20500551 0.0 1.0 httemp 5000613

* name type scale ival iflag limit

20500560 "unnamed" sum 1.0 323.49677 0 0

* a0 scale name param

20500561 0.0 1.0 httemp 5000713

* name type scale ival iflag limit

20500570 "unnamed" sum 1.0 323.42453 0 0

* a0 scale name param

20500571 0.0 1.0 httemp 5000813

* name type scale ival iflag limit

20500580 "unnamed" sum 1.0 323.33942 0 0

* a0 scale name param

20500581 0.0 1.0 httemp 5000913

* name type scale ival iflag limit

20500590 "unnamed" sum 1.0 323.29184 0 0

* a0 scale name param

20500591 0.0 1.0 httemp 5001013

* name type scale ival iflag limit

20500600 "unnamed" sum 1.0 323.4418 0 0

* a0 scale name param

20500601 0.0 1.0 httemp 5000105

* name type scale ival iflag limit

20500610 "unnamed" sum 1.0 323.50943 0 0

* a0 scale name param

20500611 0.0 1.0 httemp 5000205

* name type scale ival iflag limit

20500620 "unnamed" sum 1.0 323.55914 0 0

* a0 scale name param

20500621 0.0 1.0 httemp 5000305

* name type scale ival iflag limit

20500630 "unnamed" sum 1.0 323.58707 0 0

* a0 scale name param

20500631 0.0 1.0 httemp 5000405

* name type scale ival iflag limit

20500640 "unnamed" sum 1.0 323.59106 0 0

* a0 scale name param

20500641 0.0 1.0 httemp 5000505

* name type scale ival iflag limit

20500650 "unnamed" sum 1.0 323.57092 0 0

* a0 scale name param

20500651 0.0 1.0 httemp 5000605

* name type scale ival iflag limit

20500660 "unnamed" sum 1.0 323.52841 0 0

* a0 scale name param

20500661 0.0 1.0 httemp 5000705

* name type scale ival iflag limit

20500670 "unnamed" sum 1.0 323.46704 0 0

* a0 scale name param

20500671 0.0 1.0 httemp 5000805

* name type scale ival iflag limit

20500680 "unnamed" sum 1.0 323.39188 0 0

* a0 scale name param

20500681 0.0 1.0 httemp 5000905

* name type scale ival iflag limit

20500690 "unnamed" sum 1.0 323.3504 0 0

* a0 scale name param

20500691 0.0 1.0 httemp 5001005

* name type scale ival iflag limit

20500700 "unnamed" sum 1.0 323.52029 0 0

* a0 scale name param

20500701 0.0 1.0 httemp 3000113

* name type scale ival iflag limit

20500710 "unnamed" sum 1.0 323.58707 0 0

* a0 scale name param

20500711 0.0 1.0 httemp 3000213

* name type scale ival iflag limit

20500720 "unnamed" sum 1.0 323.62198 0 0

* a0 scale name param

20500721 0.0 1.0 httemp 3000313

* name type scale ival iflag limit

20500730 "unnamed" sum 1.0 323.62195 0 0

* a0 scale name param

20500731 0.0 1.0 httemp 3000413

* name type scale ival iflag limit

20500740 "unnamed" sum 1.0 323.58676 0 0

* a0 scale name param

20500741 0.0 1.0 httemp 3000513

* name type scale ival iflag limit

20500750 "unnamed" sum 1.0 323.51904 0 0

* a0 scale name param

20500751 0.0 1.0 httemp 3000613

* name type scale ival iflag limit

20500760 "unnamed" sum 1.0 323.42395 0 0

* a0 scale name param

20500761 0.0 1.0 httemp 3000713

* name type scale ival iflag limit

20500770 "unnamed" sum 1.0 323.30902 0 0

* a0 scale name param

20500771 0.0 1.0 httemp 3000813

* name type scale ival iflag limit
B - 4

20500780 "unnamed" sum 1.0 323.18326 0 0

* a0 scale name param

20500781 0.0 1.0 httemp 3000913

* name type scale ival iflag limit

20500790 "unnamed" sum 1.0 323.11334 0 0

* a0 scale name param

20500791 0.0 1.0 httemp 3001013

* name type scale ival iflag limit

20500800 "unnamed" sum 1.0 323.5889 0 0

* a0 scale name param

20500801 0.0 1.0 httemp 3000205

* name type scale ival iflag limit

20500810 "unnamed" sum 1.0 323.52145 0 0

* a0 scale name param

20500811 0.0 1.0 httemp 3000105

* name type scale ival iflag limit

20500820 "unnamed" sum 1.0 323.62451 0 0

* a0 scale name param

20500821 0.0 1.0 httemp 3000305

* name type scale ival iflag limit

20500830 "unnamed" sum 1.0 323.62512 0 0

* a0 scale name param

20500831 0.0 1.0 httemp 3000405

* name type scale ival iflag limit

20500840 "unnamed" sum 1.0 323.59042 0 0

* a0 scale name param

20500841 0.0 1.0 httemp 3000505

* name type scale ival iflag limit

20500850 "unnamed" sum 1.0 323.52289 0 0

* a0 scale name param

20500851 0.0 1.0 httemp 3000605

* name type scale ival iflag limit

20500860 "unnamed" sum 1.0 323.42776 0 0

* a0 scale name param

20500861 0.0 1.0 httemp 3000705

* name type scale ival iflag limit

20500870 "unnamed" sum 1.0 323.31241 0 0

* a0 scale name param

20500871 0.0 1.0 httemp 3000805

* name type scale ival iflag limit

20500880 "unnamed" sum 1.0 323.18585 0 0

* a0 scale name param

20500881 0.0 1.0 httemp 3000905

* name type scale ival iflag limit

20500890 "unnamed" sum 1.0 323.11505 0 0

* a0 scale name param

20500891 0.0 1.0 httemp 3001005

* name type scale ival iflag limit

20500900 "unnamed" sum 1.0 323.50284 0 0

* a0 scale name param

20500901 0.0 1.0 httemp 2500113

* name type scale ival iflag limit

20500910 "unnamed" sum 1.0 323.58917 0 0

* a0 scale name param

20500911 0.0 1.0 httemp 2500213

* name type scale ival iflag limit

20500920 "unnamed" sum 1.0 323.64075 0 0

* a0 scale name param

20500921 0.0 1.0 httemp 2500313

* name type scale ival iflag limit

20500930 "unnamed" sum 1.0 323.65314 0 0

* a0 scale name param

20500931 0.0 1.0 httemp 2500413

* name type scale ival iflag limit

20500940 "unnamed" sum 1.0 323.62518 0 0

* a0 scale name param

20500941 0.0 1.0 httemp 2500513

* name type scale ival iflag limit

20500950 "unnamed" sum 1.0 323.55893 0 0

* a0 scale name param

20500951 0.0 1.0 httemp 2500613

* name type scale ival iflag limit

20500960 "unnamed" sum 1.0 323.45953 0 0

* a0 scale name param

20500961 0.0 1.0 httemp 2500713

* name type scale ival iflag limit

20500970 "unnamed" sum 1.0 323.33487 0 0

* a0 scale name param

20500971 0.0 1.0 httemp 2500813

* name type scale ival iflag limit

20500980 "unnamed" sum 1.0 323.19482 0 0

* a0 scale name param

20500981 0.0 1.0 httemp 2500913

* name type scale ival iflag limit

20500990 "unnamed" sum 1.0 323.11862 0 0

* a0 scale name param

20500991 0.0 1.0 httemp 2501013

* name type scale ival iflag limit

20501000 "unnamed" sum 1.0 323.51813 0 0

* a0 scale name param

20501001 0.0 1.0 httemp 2500105

* name type scale ival iflag limit

20501010 "unnamed" sum 1.0 323.60406 0 0

* a0 scale name param

20501011 0.0 1.0 httemp 2500205

* name type scale ival iflag limit

20501020 "unnamed" sum 1.0 323.65451 0 0

* a0 scale name param

20501021 0.0 1.0 httemp 2500305

* name type scale ival iflag limit

20501030 "unnamed" sum 1.0 323.66528 0 0

* a0 scale name param

20501031 0.0 1.0 httemp 2500405

* name type scale ival iflag limit

20501040 "unnamed" sum 1.0 323.63525 0 0

* a0 scale name param

20501041 0.0 1.0 httemp 2500505

* name type scale ival iflag limit

20501050 "unnamed" sum 1.0 323.56671 0 0

* a0 scale name param

20501051 0.0 1.0 httemp 2500605

* name type scale ival iflag limit

20501060 "unnamed" sum 1.0 323.465 0 0

* a0 scale name param

20501061 0.0 1.0 httemp 2500705

* name type scale ival iflag limit

20501070 "unnamed" sum 1.0 323.3382 0 0

* a0 scale name param

20501071 0.0 1.0 httemp 2500805

* name type scale ival iflag limit

20501080 "unnamed" sum 1.0 323.19641 0 0

* a0 scale name param

20501081 0.0 1.0 httemp 2500905

* name type scale ival iflag limit

20501090 "unnamed" sum 1.0 323.11926 0 0

* a0 scale name param

20501091 0.0 1.0 httemp 2501005

* name type scale ival iflag limit

20501100 "unnamed" sum 1.0 323.6972 0 0

* a0 scale name param

20501101 0.0 1.0 httemp 2500409

* name type scale ival iflag limit

20501110 "unnamed" powerr 1.0 0.52376056 0 0

* input param power

20501111 cntrlvar 114 -0.23

* name type scale ival iflag limit

20501120 "unnamed" powerr 1.0 25.589294 0 0

* input param power

20501121 htrnr 2500400 0.35

* name type scale ival iflag limit

20501130 "T_ONBR" sum 1.0 478.85593 0 0

* a0 scale name param

20501131 0.0 1.0 sattemp 25040000

20501132 0.182 cntrlvar 115

* name type scale ival iflag limit

20501140 "unnamed" sum 1.0 16.640322 0 0

* a0 scale name param

20501141 0.0 1.0e-5 p 25040000

* name type scale ival iflag limit

20501150 "unnamed" mult 1.0 13.402663 0 0

* input param input param

20501151 cntrlvar 111 cntrlvar 112

* name type scale ival iflag limit

20501160 "unnamed" sum 1.0 0.60251117 0 0

* a0 scale name param

20501161 0.0 1.0 httemp 2500401
B - 5

20501162 -1.0 tempf 10010000

* name type scale ival iflag limit

20501170 "unnamed" sum 1.0 155.84138 0 0

* a0 scale name param

20501171 0.0 1.0 cntrlvar 113

20501172 -1.0 tempf 10010000

* name type scale ival iflag limit

20501180 "unnamed" powerr 1.0 1.6597203 0 0

* input param power

20501181 cntrlvar 116 -1.0

* name type scale ival iflag limit

20501190 "ONBR" mult 1.0 258.65311 0 0

* input param input param

20501191 cntrlvar 117 cntrlvar 118

20600000 expanded

******************************* Variable Trips 

*******************************n: Pressure_signal

* var param r var param acon l timeo

20600010 p 10010000 le null 0 9.0 l -1.0

*n: Scram_delay

* var param r var param acon l timeo

20600020 time 0 gt timeof 1001 0.35 l -1.0

*n: A120 Power_signal

* var param r var param acon l timeo

20600030 rktpow 0 ge null 0 2.16e6 l -1.0

*n: LOOS OF COOLANT FLOW

* var param r var param acon l timeo

20600040 time 0 ge null 0 160.0 l -1.0

*n: RIA_FAST

* var param r var param acon l timeo

20600050 time 0 ge null 0 160.0 l -1.0

*n: RIA_SLOW

* var param r var param acon l timeo

20600060 time 0 ge null 0 160.0 l -1.0

****************************** Logical Trips 

******************************n: SCRAM

* trip1 oper trip2 l timeo

20610010 3 or 1 l -1.0

******************************* General Tables 

*******************************n: ENVI

* type trip

20200100 temp 0

* Time Temperature

20200101 0.0 300.0

*n: PK + PAR

* type trip factor1 factor2

20200200 reac-t 2 1.0 -2.0

* Time Reactivity

20200201 0.0 0.0

20200202 0.01 5.0e-3

20200203 0.02 0.01

20200204 0.03 0.022

20200205 0.04 0.035

20200206 0.05 0.05

20200207 0.06 0.07

20200208 0.07 0.09

20200209 0.08 0.11

20200210 0.09 0.145

20200211 0.1 0.165

20200212 0.11 0.2

20200213 0.12 0.23

20200214 0.13 0.275

20200215 0.14 0.31

20200216 0.15 0.35

20200217 0.16 0.4

20200218 0.17 0.45

20200219 0.18 0.49

20200220 0.19 0.525

20200221 0.2 0.565

20200222 0.21 0.6

20200223 0.22 0.64

20200224 0.23 0.675

20200225 0.24 0.72

20200226 0.25 0.75

20200227 0.26 0.79

20200228 0.27 0.825

20200229 0.28 0.85

20200230 0.29 0.88

20200231 0.3 0.9

20200232 0.35 0.975

20200233 0.36 0.983

20200234 0.37 0.99

20200235 0.38 0.999

20200236 0.39 1.0

*n: PB

* type trip factor1 factor2

20200300 reac-t 2 1.0 -3.5

* Time Reactivity

20200301 0.0 0.0

20200302 0.01 0.0

20200303 0.02 0.0

20200304 0.03 0.0

20200305 0.04 0.0

20200306 0.05 0.0

20200307 0.06 1.0e-3

20200308 0.07 2.0e-3

20200309 0.08 3.0e-3

20200310 0.09 4.0e-3

20200311 0.1 5.0e-3

20200312 0.11 6.0e-3

20200313 0.12 7.0e-3

20200314 0.13 8.0e-3

20200315 0.14 9.0e-3

20200316 0.15 0.01

20200317 0.16 0.013

20200318 0.17 0.016

20200319 0.18 0.019

20200320 0.19 0.022

20200321 0.2 0.025

20200322 0.21 0.03

20200323 0.22 0.04

20200324 0.23 0.05

20200325 0.24 0.06

20200326 0.25 0.07

20200327 0.26 0.085

20200328 0.27 0.1

20200329 0.28 0.118

20200330 0.29 0.135

20200331 0.3 0.157

20200332 0.35 0.3

20200333 0.36 0.32

20200334 0.37 0.345

20200335 0.38 0.38

20200336 0.39 0.41

20200337 0.4 0.45

20200338 0.41 0.49

20200339 0.42 0.515

20200340 0.43 0.55

20200341 0.44 0.59

20200342 0.45 0.62

20200343 0.46 0.66

20200344 0.47 0.7

20200345 0.48 0.735

20200346 0.49 0.77

20200347 0.5 0.8

20200348 0.51 0.825

20200349 0.52 0.86

20200350 0.53 0.89

20200351 0.54 0.905

20200352 0.55 0.925

20200353 0.56 0.935

20200354 0.57 0.95

20200355 0.58 0.963

20200356 0.59 0.975

20200357 0.6 0.985

20200358 0.63 1.0

*n: Reactivity_Slow

* type trip

20200400 reac-t 6

* Time Reactivity

20200401 -1.0 0.0

20200402 0.0 0.0

20200403 1.0 0.04

20200404 2.0 0.08

20200405 3.0 0.12

20200406 4.0 0.16
B - 6

20200407 5.0 0.2

20200408 6.0 0.24

20200409 7.0 0.28

20200410 8.0 0.32

20200411 9.0 0.36

20200412 10.0 0.4

20200413 11.0 0.44

20200414 12.0 0.48

20200415 13.0 0.52

20200416 14.0 0.56

20200417 15.0 0.6

20200418 16.0 0.64

20200419 17.0 0.68

20200420 18.0 0.72

20200421 19.0 0.76

20200422 20.0 0.8

20200423 21.0 0.84

20200424 22.0 0.88

20200425 23.0 0.92

20200426 24.0 0.96

20200427 25.0 1.0

20200428 26.0 1.04

20200429 27.0 1.08

20200430 28.0 1.12

20200431 29.0 1.16

20200432 30.0 1.2

20200433 31.0 1.24

20200434 32.0 1.28

20200435 33.0 1.32

20200436 34.0 1.36

20200437 35.0 1.4

20200438 36.0 1.44

20200439 37.0 1.48

20200440 38.0 1.52

20200441 39.0 1.56

20200442 40.0 1.6

20200443 41.0 1.64

20200444 42.0 1.68

20200445 43.0 1.72

20200446 44.0 1.76

20200447 45.0 1.8

20200448 46.0 1.84

20200449 47.0 1.88

20200450 48.0 1.92

20200451 49.0 1.96

20200452 50.0 2.0

*n: Reactivity_Fast

* type trip

20200500 reac-t 5

* Time Reactivity

20200501 -1.0 0.0

20200502 0.0 0.0

20200503 0.01 0.04

20200504 0.02 0.08

20200505 0.03 0.12

20200506 0.04 0.16

20200507 0.05 0.2

20200508 0.06 0.24

20200509 0.07 0.28

20200510 0.08 0.32

20200511 0.09 0.36

20200512 0.1 0.4

20200513 0.11 0.44

20200514 0.12 0.48

20200515 0.13 0.52

20200516 0.14 0.56

20200517 0.15 0.6

20200518 0.16 0.64

20200519 0.17 0.68

20200520 0.18 0.72

20200521 0.19 0.76

20200522 0.2 0.8

20200523 0.21 0.84

20200524 0.22 0.88

20200525 0.23 0.92

20200526 0.24 0.96

20200527 0.25 1.0

20200528 0.26 1.04

20200529 0.27 1.08

20200530 0.28 1.12

20200531 0.29 1.16

20200532 0.3 1.2

20200533 0.31 1.24

20200534 0.32 1.28

20200535 0.33 1.32

20200536 0.34 1.36

20200537 0.35 1.4

20200538 0.36 1.44

20200539 0.37 1.48

20200540 0.375 1.5

*n: Power_for_SS

* type trip

20200600 power 0

* Time Power

20200601 -1.0 1.8e6

20200602 0.0 1.8e6

20200603 1.0 1.8e6

20200604 1.0e6 1.8e6

************************** Materials **************************n: 

Fuel

* type tflag vflag

20100100 tbl/fctn 1 1

* thcond

20100101 59.0

* temp capacity

20100151 273.0 0.35837293

20100152 303.0 0.35837293

20100153 313.0 0.37012693

20100154 323.0 0.38188093

20100155 333.0 0.39363493

20100156 343.0 0.40538893

20100157 353.0 0.41714293

20100158 363.0 0.42889693

20100159 373.0 0.44065093

20100160 383.0 0.45240493

20100161 393.0 0.46415893

20100162 403.0 0.47591293

20100163 413.0 0.48766693

20100164 423.0 0.49942093

20100165 433.0 0.51117493

20100166 443.0 0.52292893

20100167 453.0 0.53468293

20100168 463.0 0.54643693

20100169 473.0 0.55819093

20100170 523.0 0.61696093

20100171 573.0 0.67573093

20100172 623.0 0.73450093

20100173 673.0 0.79327093

20100174 723.0 0.85204093

20100175 773.0 0.91081093

20100176 823.0 0.96958093

20100177 873.0 1.0283509

20100178 923.0 1.0871209

20100179 973.0 1.1458909

20100180 2000.0 1.1458909

*n: AGN cladding

* type tflag vflag

20100200 tbl/fctn 1 1

* thcond

20100201 130.0

* heat Capacity

20100251 2.3496e6

*n: Aluminium

* type tflag vflag

20100300 tbl/fctn 1 1

* temp thcond

20100301 273.0 237.0

20100302 300.0 237.0

20100303 350.0 240.0

20100304 400.0 240.0

20100305 500.0 236.0

20100306 600.0 231.0

20100307 800.0 218.0

20100308 1200.0 218.0

* temp capacity

20100351 273.0 2.4219e6
B - 7

20100352 298.0 2.4219e6

20100353 350.0 2.51262e6

20100354 400.0 2.57985e6

20100355 500.0 2.68596e6

20100356 600.0 2.7918e6

20100357 1000.0 2.7918e6

*n: SAW

* type tflag vflag

20100400 tbl/fctn 1 1

* temp thcond

20100401 273.0 170.0

20100402 900.0 170.0

* temp capacity

20100451 273.0 2.4192e6

20100452 900.0 2.4192e6

************************************* Hydraulic Components 

************************************* name type

0050000 "unnamed" tmdpvol

* area length vol

0050101 20.0 20.0 0.0

* az-angle inc-angle dz

0050102 0.0 90.0 20.0

* x-rough x-hd flags

0050103 0.0 0.0 0

* cword

0050200 3

* srch press temp

0050201 0.0 1.4e6 323.15

0050202 0.99 1.4e6 323.15

0050203 1.0 1.4e6 323.15

* name type

0060000 "unnamed" tmdpjun

* from to area jefvcahs

0060101 5010002 10010001 2.294e-3 0

* control

0060200 1

* srch mfl mfv unused

0060201 0.0 7.41 0.0 0.0

* name type

0100000 "unnamed" pipe

* ncells

0100001 6

* x-area volid

0100101 2.294e-3 6

* x-length volid

0100301 0.3 1

0100302 0.5 4

0100303 0.4 5

0100304 0.2 6

* volume volid

0100401 0.0 6

* azim-angle volid

0100501 0.0 6

* vert-angle volid

0100601 -90.0 6

* x-wall xhd volid

0100801 1.0e-5 0.027 6

* x-flags volid

0101001 0 6

* ebt press water-ie steam-ie void none id

0101201 000 1.698744e6 2.085118e5 2.596097e6 0.0 0.0 1

0101202 000 1.700844e6 2.085396e5 2.596122e6 0.0 0.0 2

0101203 000 1.703468e6 2.085674e5 2.596154e6 0.0 0.0 3

0101204 000 1.706092e6 2.085951e5 2.596185e6 0.0 0.0 4

0101205 000 1.708454e6 2.086174e5 2.596214e6 0.0 0.0 5

0101206 000 1.710028e6 2.086285e5 2.596232e6 0.0 0.0 6

* jefvcahs jun num

0101101 00000000 5

* vl vv unused junid

0101301 3.6371021 3.6371021 0.0 1

0101302 3.63711 3.63711 0.0 2

0101303 3.6371169 3.6371169 0.0 3

0101304 3.6371241 3.6371241 0.0 4

0101305 3.6371293 3.6371293 0.0 5

* hd corr gas slope junid

0101401 0.027 0.0 1.0 1.0 5

* name type

0150000 "unnamed" branch

* njuns 

0150001 4

* area length vol

0150101 2.294e-3 0.1 0.0

* az-angle inc-angle dz

0150102 0.0 -90.0 -0.1

* x-rough x-hd flags

0150103 0.0 0.0 0

* ebt press water-ie steam-ie void

0150200 000 1.710953e6 2.086334e5 2.596243e6 

0.0

* from to area

0151101 15010001 10060002 2.294e-3

* fwd. loss rev. loss efvcahs

0151102 0.0 0.0 0

* hyd diam ccfl wght ccfl gas ccfl slope

0151110 0.027 0.0 1.0 1.0

* vl vv unused

0151201 -3.6371312 -3.6371312 0.0

* from to area

0152101 15010002 20010001 5.24e-4

* fwd. loss rev. loss efvcahs

0152102 0.4 0.4 0

* vl vv unused

0152201 6.1487789 6.1487789 0.0

* from to area

0153101 15010002 25010001 4.54e-4

* fwd. loss rev. loss efvcahs

0153102 0.4 0.4 0

* vl vv unused

0153201 6.1307321 6.1307321 0.0

* from to area

0154101 15010002 30010001 3.83e-4

* fwd. loss rev. loss efvcahs

0154102 0.4 0.4 0

* vl vv unused

0154201 6.1051373 6.1051373 0.0

* name type

0200000 "unnamed" pipe

* ncells

0200001 12

* x-area volid

0200101 5.24e-4 12

* x-length volid

0200301 0.05 1

0200302 0.1 11

0200303 0.05 12

* volume volid

0200401 0.0 12

* azim-angle volid

0200501 0.0 12

* vert-angle volid

0200601 -90.0 12

* x-wall xhd volid

0200801 1.0e-5 4.827e-3 12

* x-flags volid

0201001 0 12

* ebt press temp none none none id

0201201 003 1.689443e6 323.045 0.0 0.0 0.0 1

* ebt press water-ie steam-ie void none id

0201202 000 1.682478e6 2.086602e5 2.595899e6 0.0 0.0 2

* ebt press water-ie steam-ie void none id

0201203 000 1.673191e6 2.086929e5 2.595784e6 0.0 0.0 3

* ebt press water-ie steam-ie void none id

0201204 000 1.663904e6 2.087463e5 2.595668e6 0.0 0.0 4

* ebt press water-ie steam-ie void none id

0201205 000 1.654618e6 2.088172e5 2.595551e6 0.0 0.0 5

* ebt press water-ie steam-ie void none id

0201206 000 1.645331e6 2.089011e5 2.595432e6 0.0 0.0 6

* ebt press water-ie steam-ie void none id

0201207 000 1.636045e6 2.089922e5 2.595312e6 0.0 0.0 7

* ebt press water-ie steam-ie void none id

0201208 000 1.626759e6 2.090844e5 2.595191e6 0.0 0.0 8

* ebt press water-ie steam-ie void none id

0201209 000 1.617473e6 2.091712e5 2.595068e6 0.0 0.0 9

* ebt press water-ie steam-ie void none id

0201210 000 1.608187e6 2.092468e5 2.594944e6 0.0 0.0 10

* ebt press water-ie steam-ie void none id
B - 8

0201211 000 1.598902e6 2.093061e5 2.594818e6 0.0 0.0 11

* ebt press water-ie steam-ie void none id

0201212 000 1.591937e6 2.093155e5 2.594723e6 0.0 0.0 12

* area jun

0200201 5.24e-4 11

* jefvcahs jun num

0201101 00000000 11

* vl vv unused junid

0201301 6.1488385 6.1488385 0.0 1

0201302 6.1488714 6.1488714 0.0 2

0201303 6.1489172 6.1489172 0.0 3

0201304 6.1489778 6.1489778 0.0 4

0201305 6.1490493 6.1490493 0.0 5

0201306 6.1491299 6.1491299 0.0 6

0201307 6.1492157 6.1492157 0.0 7

0201308 6.149302 6.149302 0.0 8

0201309 6.1493845 6.1493845 0.0 9

0201310 6.1494598 6.1494598 0.0 10

0201311 6.1495237 6.1495237 0.0 11

* hd corr gas slope junid

0201401 4.827e-3 0.0 1.0 1.0 11

* name type

0250000 "unnamed" pipe

* ncells

0250001 12

* x-area volid

0250101 4.54e-4 12

* x-length volid

0250301 0.05 1

0250302 0.1 11

0250303 0.05 12

* volume volid

0250401 0.0 12

* azim-angle volid

0250501 0.0 12

* vert-angle volid

0250601 -90.0 12

* x-wall xhd volid

0250801 1.0e-5 4.802e-3 12

* x-flags volid

0251001 0 12

* ebt press water-ie steam-ie void none id

0251201 000 1.689598e6 2.086388e5 2.595986e6 0.0 0.0 1

0251202 000 1.682626e6 2.086712e5 2.595901e6 0.0 0.0 2

0251203 000 1.673329e6 2.087246e5 2.595786e6 0.0 0.0 3

0251204 000 1.664032e6 2.088165e5 2.59567e6 0.0 0.0 4

0251205 000 1.654736e6 2.0894e5 2.595552e6 0.0 0.0 5

0251206 000 1.645439e6 2.090854e5 2.595434e6 0.0 0.0 6

0251207 000 1.636143e6 2.092415e5 2.595314e6 0.0 0.0 7

0251208 000 1.626848e6 2.093963e5 2.595192e6 0.0 0.0 8

0251209 000 1.617552e6 2.095376e5 2.595069e6 0.0 0.0 9

0251210 000 1.608257e6 2.096547e5 2.594945e6 0.0 0.0 10

0251211 000 1.598962e6 2.097386e5 2.594819e6 0.0 0.0 11

0251212 000 1.591991e6 2.09739e5 2.594724e6 0.0 0.0 12

* area jun

0250201 4.54e-4 11

* jefvcahs jun num

0251101 00000000 11

* vl vv unused junid

0251301 6.1307912 6.1307912 0.0 1

0251302 6.1308308 6.1308308 0.0 2

0251303 6.1308908 6.1308908 0.0 3

0251304 6.1309767 6.1309767 0.0 4

0251305 6.1310835 6.1310835 0.0 5

0251306 6.1312056 6.1312056 0.0 6

0251307 6.1313348 6.1313348 0.0 7

0251308 6.1314626 6.1314626 0.0 8

0251309 6.1315818 6.1315818 0.0 9

0251310 6.1316848 6.1316848 0.0 10

0251311 6.1317654 6.1317654 0.0 11

* hd corr gas slope junid

0251401 4.802e-3 0.0 1.0 1.0 11

* name type

0300000 "unnamed" pipe

* ncells

0300001 12

* x-area volid

0300101 3.83e-4 12

* x-length volid

0300301 0.05 1

0300302 0.1 11

0300303 0.05 12

* volume volid

0300401 0.0 12

* azim-angle volid

0300501 0.0 12

* vert-angle volid

0300601 -90.0 12

* x-wall xhd volid

0300801 1.0e-5 4.767e-3 12

* x-flags volid

0301001 0 12

* ebt press water-ie steam-ie void none id

0301201 000 1.689816e6 2.086581e5 2.595989e6 0.0 0.0 1

0301202 000 1.682834e6 2.087158e5 2.595904e6 0.0 0.0 2

0301203 000 1.673524e6 2.087883e5 2.595789e6 0.0 0.0 3

0301204 000 1.664214e6 2.088898e5 2.595672e6 0.0 0.0 4

0301205 000 1.654904e6 2.090142e5 2.595555e6 0.0 0.0 5

0301206 000 1.645594e6 2.091535e5 2.595436e6 0.0 0.0 6

0301207 000 1.636285e6 2.092983e5 2.595316e6 0.0 0.0 7

0301208 000 1.626976e6 2.094388e5 2.595194e6 0.0 0.0 8

0301209 000 1.617667e6 2.095653e5 2.595071e6 0.0 0.0 9

0301210 000 1.608359e6 2.096694e5 2.594946e6 0.0 0.0 10

0301211 000 1.599051e6 2.097441e5 2.59482e6 0.0 0.0 11

0301212 000 1.59207e6 2.097471e5 2.594725e6 0.0 0.0 12

* area jun

0300201 3.83e-4 11

* jefvcahs jun num

0301101 00000000 11

* vl vv unused junid

0301301 6.1052089 6.1052089 0.0 1

0301302 6.1052651 6.1052651 0.0 2

0301303 6.1053376 6.1053376 0.0 3

0301304 6.1054296 6.1054296 0.0 4

0301305 6.1055369 6.1055369 0.0 5

0301306 6.1056542 6.1056542 0.0 6

0301307 6.1057749 6.1057749 0.0 7

0301308 6.1058931 6.1058931 0.0 8

0301309 6.1060019 6.1060019 0.0 9

0301310 6.1060958 6.1060958 0.0 10

0301311 6.1061702 6.1061702 0.0 11

* hd corr gas slope junid

0301401 4.767e-3 0.0 1.0 1.0 11

* name type

0350000 "unnamed" branch

* njuns 

0350001 4

* area length vol

0350101 2.294e-3 0.05 0.0

* az-angle inc-angle dz

0350102 0.0 -90.0 -0.05

* x-rough x-hd flags

0350103 0.0 0.0 0

* ebt press water-ie steam-ie void

0350200 000 1.592632e6 2.095778e5 2.594733e6 

0.0

* from to area

0351101 35010002 40010001 2.294e-3

* fwd. loss rev. loss efvcahs

0351102 1.5 1.5 0

* vl vv unused

0351201 3.6376903 3.6376903 0.0

* from to area

0352101 35010001 20120002 5.24e-4

* fwd. loss rev. loss efvcahs

0352102 0.5 0.5 0

* vl vv unused

0352201 -6.1495485 -6.1495485 0.0

* from to area

0353101 35010001 25120002 4.54e-4

* fwd. loss rev. loss efvcahs

0353102 0.5 0.5 0

* vl vv unused

0353201 -6.131784 -6.131784 0.0

* from to area

0354101 35010001 30120002 3.83e-4
B - 9

* fwd. loss rev. loss efvcahs

0354102 0.5 0.5 0

* vl vv unused

0354201 -6.1061902 -6.1061902 0.0

* name type

0400000 "unnamed" branch

* njuns 

0400001 0

* area length vol

0400101 4.418e-3 0.05 0.0

* az-angle inc-angle dz

0400102 0.0 -90.0 -0.05

* x-rough x-hd flags

0400103 0.0 0.0 0

* ebt press water-ie steam-ie void

0400200 000 1.589762e6 2.095778e5 2.594694e6 

0.0

* name type

0450000 "unnamed" branch

* njuns 

0450001 5

* area length vol

0450101 1.81e-3 0.05 0.0

* az-angle inc-angle dz

0450102 0.0 90.0 0.05

* x-rough x-hd flags

0450103 0.0 0.0 0

* ebt press water-ie steam-ie void

0450200 000 1.562884e6 2.095779e5 2.594318e6 

0.0

* from to area

0451101 45010001 40010001 1.81e-3

* fwd. loss rev. loss efvcahs

0451102 1.5 1.5 0

* vl vv unused

0451201 -4.6104264 -4.6104264 0.0

* from to area

0452101 45010002 50010001 3.12e-4

* fwd. loss rev. loss efvcahs

0452102 0.5 0.5 0

* vl vv unused

0452201 11.260211 11.260211 0.0

* from to area

0453101 45010002 55010001 2.42e-4

* fwd. loss rev. loss efvcahs

0453102 0.5 0.5 0

* vl vv unused

0453201 11.155989 11.155989 0.0

* from to area

0454101 45010002 60010001 1.71e-4

* fwd. loss rev. loss efvcahs

0454102 0.5 0.5 0

* vl vv unused

0454201 10.971682 10.971682 0.0

* from to area

0455101 45010002 80010001 1.1e-5

* fwd. loss rev. loss efvcahs

0455102 0.5 0.5 0

* vl vv unused

0455201 23.26129 23.26129 0.0

* name type

0500000 "unnamed" pipe

* ncells

0500001 12

* x-area volid

0500101 3.12e-4 12

* x-length volid

0500301 0.05 1

0500302 0.1 11

0500303 0.05 12

* volume volid

0500401 0.0 12

* azim-angle volid

0500501 0.0 12

* vert-angle volid

0500601 90.0 12

* x-wall xhd volid

0500801 1.0e-5 4.717e-3 12

* x-flags volid

0501001 0 12

* ebt press water-ie steam-ie void none id

0501201 000 1.470377e6 2.095963e5 2.592927e6 0.0 0.0 1

0501202 000 1.444268e6 2.096746e5 2.592505e6 0.0 0.0 2

0501203 000 1.409458e6 2.097678e5 2.591922e6 0.0 0.0 3

0501204 000 1.374648e6 2.098706e5 2.591312e6 0.0 0.0 4

0501205 000 1.339838e6 2.099767e5 2.590677e6 0.0 0.0 5

0501206 000 1.305028e6 2.100796e5 2.590014e6 0.0 0.0 6

0501207 000 1.270217e6 2.101732e5 2.589321e6 0.0 0.0 7

0501208 000 1.235407e6 2.102518e5 2.588597e6 0.0 0.0 8

0501209 000 1.200597e6 2.10311e5 2.587841e6 0.0 0.0 9

0501210 000 1.165786e6 2.103481e5 2.58705e6 0.0 0.0 10

0501211 000 1.130976e6 2.103731e5 2.586223e6 0.0 0.0 11

0501212 000 1.104867e6 2.10377e5 2.585578e6 0.0 0.0 12

* area jun

0500201 3.12e-4 11

* jefvcahs jun num

0501101 00000000 11

* vl vv unused junid

0501301 11.260675 11.260675 0.0 1

0501302 11.260897 11.260897 0.0 2

0501303 11.261178 11.261178 0.0 3

0501304 11.261471 11.261471 0.0 4

0501305 11.261768 11.261768 0.0 5

0501306 11.262062 11.262062 0.0 6

0501307 11.262344 11.262344 0.0 7

0501308 11.262608 11.262608 0.0 8

0501309 11.262847 11.262847 0.0 9

0501310 11.26306 11.26306 0.0 10

0501311 11.263257 11.263257 0.0 11

* hd corr gas slope junid

0501401 4.717e-3 0.0 1.0 1.0 11

* name type

0550000 "unnamed" pipe

* ncells

0550001 12

* x-area volid

0550101 2.42e-4 12

* x-length volid

0550301 0.05 1

0550302 0.1 11

0550303 0.05 12

* volume volid

0550401 0.0 12

* azim-angle volid

0550501 0.0 12

* vert-angle volid

0550601 90.0 12

* x-wall xhd volid

0550801 1.0e-5 4.64e-3 12

* x-flags volid

0551001 0 12

* ebt press water-ie steam-ie void none id

0551201 000 1.472093e6 2.09595e5 2.592954e6 0.0 0.0 1

0551202 000 1.445911e6 2.096632e5 2.592532e6 0.0 0.0 2

0551203 000 1.411005e6 2.097448e5 2.591948e6 0.0 0.0 3

0551204 000 1.376099e6 2.09836e5 2.591338e6 0.0 0.0 4

0551205 000 1.341192e6 2.099321e5 2.590702e6 0.0 0.0 5

0551206 000 1.306286e6 2.10028e5 2.590038e6 0.0 0.0 6

0551207 000 1.271379e6 2.101188e5 2.589344e6 0.0 0.0 7

0551208 000 1.236472e6 2.101997e5 2.58862e6 0.0 0.0 8

0551209 000 1.201565e6 2.102668e5 2.587862e6 0.0 0.0 9

0551210 000 1.166658e6 2.103176e5 2.58707e6 0.0 0.0 10

0551211 000 1.131751e6 2.103593e5 2.586242e6 0.0 0.0 11

0551212 000 1.10557e6 2.103754e5 2.585596e6 0.0 0.0 12

* area jun

0550201 2.42e-4 11

* jefvcahs jun num

0551101 00000000 11

* vl vv unused junid

0551301 11.156439 11.156439 0.0 1

0551302 11.156647 11.156647 0.0 2

0551303 11.156912 11.156912 0.0 3

0551304 11.157188 11.157188 0.0 4

0551305 11.157471 11.157471 0.0 5

0551306 11.157754 11.157754 0.0 6

0551307 11.158031 11.158031 0.0 7
B - 10

0551308 11.158295 11.158295 0.0 8

0551309 11.158542 11.158542 0.0 9

0551310 11.15877 11.15877 0.0 10

0551311 11.158986 11.158986 0.0 11

* hd corr gas slope junid

0551401 4.64e-3 0.0 1.0 1.0 11

* name type

0600000 "unnamed" pipe

* ncells

0600001 12

* x-area volid

0600101 1.71e-4 12

* x-length volid

0600301 0.05 1

0600302 0.1 11

0600303 0.05 12

* volume volid

0600401 0.0 12

* azim-angle volid

0600501 0.0 12

* vert-angle volid

0600601 90.0 12

* x-wall xhd volid

0600801 1.0e-5 4.506e-3 12

* x-flags volid

0601001 0 12

* ebt press water-ie steam-ie void none id

0601201 000 1.475083e6 2.095953e5 2.593001e6 0.0 0.0 1

0601202 000 1.448776e6 2.096526e5 2.592579e6 0.0 0.0 2

0601203 000 1.413704e6 2.097188e5 2.591994e6 0.0 0.0 3

0601204 000 1.37863e6 2.097916e5 2.591384e6 0.0 0.0 4

0601205 000 1.343557e6 2.098679e5 2.590746e6 0.0 0.0 5

0601206 000 1.308484e6 2.099442e5 2.590081e6 0.0 0.0 6

0601207 000 1.27341e6 2.100174e5 2.589386e6 0.0 0.0 7

0601208 000 1.238336e6 2.100842e5 2.588659e6 0.0 0.0 8

0601209 000 1.203262e6 2.10142e5 2.5879e6 0.0 0.0 9

0601210 000 1.168188e6 2.10189e5 2.587106e6 0.0 0.0 10

0601211 000 1.133113e6 2.102301e5 2.586275e6 0.0 0.0 11

0601212 000 1.106807e6 2.102442e5 2.585627e6 0.0 0.0 12

* area jun

0600201 1.71e-4 11

* jefvcahs jun num

0601101 00000000 11

* vl vv unused junid

0601301 10.972111 10.972111 0.0 1

0601302 10.972301 10.972301 0.0 2

0601303 10.972545 10.972545 0.0 3

0601304 10.972795 10.972795 0.0 4

0601305 10.97305 10.97305 0.0 5

0601306 10.973306 10.973306 0.0 6

0601307 10.973557 10.973557 0.0 7

0601308 10.973801 10.973801 0.0 8

0601309 10.974033 10.974033 0.0 9

0601310 10.974254 10.974254 0.0 10

0601311 10.974466 10.974466 0.0 11

* hd corr gas slope junid

0601401 4.506e-3 0.0 1.0 1.0 11

* name type

0650000 "unnamed" branch

* njuns 

0650001 5

* area length vol

0650101 1.81e-3 0.1 0.0

* az-angle inc-angle dz

0650102 0.0 90.0 0.1

* x-rough x-hd flags

0650103 0.0 0.0 0

* ebt press water-ie steam-ie void

0650200 000 1.122699e6 2.103265e5 2.586021e6 

0.0

* from to area

0651101 65010002 70010001 1.81e-3

* fwd. loss rev. loss efvcahs

0651102 0.0 0.0 0

* vl vv unused

0651201 4.6117187 4.6117187 0.0

* from to area

0652101 65010001 50120002 3.12e-4

* fwd. loss rev. loss efvcahs

0652102 0.4 0.4 0

* vl vv unused

0652201 -11.263387 -11.263387 0.0

* from to area

0653101 65010001 55120002 2.42e-4

* fwd. loss rev. loss efvcahs

0653102 0.4 0.4 0

* vl vv unused

0653201 -11.159129 -11.159129 0.0

* from to area

0654101 65010001 60120002 1.71e-4

* fwd. loss rev. loss efvcahs

0654102 0.4 0.4 0

* vl vv unused

0654201 -10.974606 -10.974606 0.0

* from to area

0655101 65010001 80120002 1.1e-5

* fwd. loss rev. loss efvcahs

0655102 0.4 0.4 0

* vl vv unused

0655201 -23.267387 -23.267387 0.0

* name type

0700000 "unnamed" pipe

* ncells

0700001 6

* x-area volid

0700101 1.81e-3 6

* x-length volid

0700301 0.2 1

0700302 0.4 2

0700303 0.5 5

0700304 0.3 6

* volume volid

0700401 0.0 6

* azim-angle volid

0700501 0.0 6

* vert-angle volid

0700601 90.0 6

* x-wall xhd volid

0700801 1.0e-5 0.0 6

* x-flags volid

0701001 0 6

* ebt press water-ie steam-ie void none id

0701201 000 1.120749e6 2.103169e5 2.585973e6 0.0 0.0 1

0701202 000 1.116802e6 2.102979e5 2.585876e6 0.0 0.0 2

0701203 000 1.110882e6 2.102742e5 2.585728e6 0.0 0.0 3

0701204 000 1.104304e6 2.102504e5 2.585564e6 0.0 0.0 4

0701205 000 1.097726e6 2.102265e5 2.585398e6 0.0 0.0 5

0701206 000 1.092463e6 2.102121e5 2.585264e6 0.0 0.0 6

* jefvcahs jun num

0701101 00000000 5

* vl vv unused junid

0701301 4.6117172 4.6117172 0.0 1

0701302 4.6117153 4.6117153 0.0 2

0701303 4.6117148 4.6117148 0.0 3

0701304 4.6117158 4.6117158 0.0 4

0701305 4.6117167 4.6117167 0.0 5

* name type

0740000 "unnamed" sngljun

* from to area

0740101 70060002 75010001 0.0

* fwd. loss rev. loss efvcahs

0740102 0.0 0.0 0

* discharge thermal 

0740103 1.0 0.14

* flow vl vv unused

0740201 0 4.6117196 4.6117196 0.0

* name type

0750000 "unnamed" tmdpvol

* area length vol

0750101 20.0 20.0 0.0

* az-angle inc-angle dz

0750102 0.0 90.0 20.0

* x-rough x-hd flags

0750103 0.0 0.0 0

* cword

0750200 3
B - 11

* srch press temp

0750201 0.0 1.101e6 300.0

* name type

0800000 "unnamed" pipe

* ncells

0800001 12

* x-area volid

0800101 1.1e-5 1

0800102 3.46e-4 11

0800103 1.1e-5 12

* x-length volid

0800301 0.05 1

0800302 0.1 11

0800303 0.05 12

* volume volid

0800401 0.0 12

* azim-angle volid

0800501 0.0 12

* vert-angle volid

0800601 90.0 12

* x-wall xhd volid

0800801 1.0e-5 0.0 12

* x-flags volid

0801001 0 12

* ebt press water-ie steam-ie void none id

0801201 000 1.12475e6 2.096705e5 2.586072e6 0.0 0.0 1

0801202 000 1.34429e6 2.096706e5 2.59076e6 0.0 0.0 2

0801203 000 1.343289e6 2.096722e5 2.590741e6 0.0 0.0 3

0801204 000 1.342287e6 2.096755e5 2.590723e6 0.0 0.0 4

0801205 000 1.341286e6 2.096807e5 2.590704e6 0.0 0.0 5

0801206 000 1.340284e6 2.096875e5 2.590686e6 0.0 0.0 6

0801207 000 1.339282e6 2.09696e5 2.590667e6 0.0 0.0 7

0801208 000 1.338281e6 2.09706e5 2.590648e6 0.0 0.0 8

0801209 000 1.337279e6 2.09717e5 2.590629e6 0.0 0.0 9

0801210 000 1.336277e6 2.097289e5 2.59061e6 0.0 0.0 10

0801211 000 1.335276e6 2.097414e5 2.590592e6 0.0 0.0 11

0801212 000 1.020448e6 2.098705e5 2.583331e6 0.0 0.0 12

* area jun

0800201 3.46e-4 11

* jefvcahs jun num

0801101 00000000 11

* vl vv unused junid

0801301 0.73966569 0.73966569 0.0 1

0801302 0.73959684 0.73959684 0.0 2

0801303 0.73959726 0.73959726 0.0 3

0801304 0.73959786 0.73959786 0.0 4

0801305 0.73959857 0.73959857 0.0 5

0801306 0.73959947 0.73959947 0.0 6

0801307 0.73960048 0.73960048 0.0 7

0801308 0.73960161 0.73960161 0.0 8

0801309 0.7396028 0.7396028 0.0 9

0801310 0.73960406 0.73960406 0.0 10

0801311 0.73960543 0.73960543 0.0 11

******************************** Heat Structures 

******************************** nh np geom ssif leftcoord 

reflood

10010000 8 7 2 1 0.024 0

* mesh format

10010100 0 1

* intervals radius

10010101 6 0.026

* material interval

10010201 3 6

* rpkf interval

10010301 0.0 6

* temp interval

10010401 300.0 7

* Left Boundary Condition Data 

* bound incr type code factor node

10010501 70060000 0 101 1 0.3 1

10010502 70050000 0 101 1 0.5 2

10010503 70040000 0 101 1 0.5 3

10010504 70030000 0 101 1 0.5 4

10010505 70020000 0 101 1 0.4 5

10010506 70010000 0 101 1 0.2 6

10010507 65010000 0 101 1 0.1 7

10010508 45010000 0 101 1 0.05 8

* Right Boundary Condition Data 

* bound incr type code factor node

10010601 10010000 0 101 1 0.3 1

10010602 10020000 0 101 1 0.5 2

10010603 10030000 0 101 1 0.5 3

10010604 10040000 0 101 1 0.5 4

10010605 10050000 0 101 1 0.4 5

10010606 10060000 0 101 1 0.2 6

10010607 15010000 0 101 1 0.1 7

10010608 35010000 0 101 1 0.05 8

* source mult dmhl dmhr num

10010701 0 0.0 0.0 0.0 8

* Left Additional Boundary Condition Data 

10010800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10010801 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 8

* Right Additional Boundary Condition Data 

10010900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10010901 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 8

*n: 5

* nh np geom ssif leftcoord reflood

10025000 10 17 2 1 0.033 0

* mesh format

10025100 0 1

* intervals radius

10025101 4 0.0336

10025102 8 0.0344

10025103 4 0.035

* material interval

10025201 2 4

10025202 1 12

10025203 2 16

* rpkf interval

10025301 0.0 4

10025302 1.0 12

10025303 0.0 16

* temp interval

10025401 300.0 17

* Left Boundary Condition Data 

* bound incr type code factor node

10025501 25110000 0 101 1 0.1 1

10025502 25100000 0 101 1 0.1 2

10025503 25090000 0 101 1 0.1 3

10025504 25080000 0 101 1 0.1 4

10025505 25070000 0 101 1 0.1 5

10025506 25060000 0 101 1 0.1 6

10025507 25050000 0 101 1 0.1 7

10025508 25040000 0 101 1 0.1 8

10025509 25030000 0 101 1 0.1 9

10025510 25020000 0 101 1 0.1 10

* Right Boundary Condition Data 

* bound incr type code factor node

10025601 20110000 0 101 1 0.1 1

10025602 20100000 0 101 1 0.1 2

10025603 20090000 0 101 1 0.1 3

10025604 20080000 0 101 1 0.1 4

10025605 20070000 0 101 1 0.1 5

10025606 20060000 0 101 1 0.1 6

10025607 20050000 0 101 1 0.1 7

10025608 20040000 0 101 1 0.1 8

10025609 20030000 0 101 1 0.1 9

10025610 20020000 0 101 1 0.1 10

* source mult dmhl dmhr num

10025701 1000 0.026176409 0.0 0.0 1

10025702 1000 0.036591412 0.0 0.0 2

10025703 1000 0.044041994 0.0 0.0 3

10025704 1000 0.047924554 0.0 0.0 5

10025705 1000 0.044041994 0.0 0.0 6

10025706 1000 0.036591412 0.0 0.0 7

10025707 1000 0.026176409 0.0 0.0 8

10025708 1000 0.013640753 0.0 0.0 9

10025709 1000 6.890509e-3 0.0 0.0 10

* Left Additional Boundary Condition Data 

10025800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10025801 9.816e-3 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* Right Additional Boundary Condition Data 

10025900 0
B - 12

* hthd hlf hlr gslf gslr glcf glcr lbf node

10025901 0.010697 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* nh np geom ssif leftcoord reflood

10026000 2 7 2 1 0.033 0

* mesh format

10026100 0 1

* intervals radius

10026101 6 0.035

* material interval

10026201 2 6

* rpkf interval

10026301 0.0 6

* temp interval

10026401 300.0 7

* Left Boundary Condition Data 

* bound incr type code factor node

10026501 25010000 0 101 1 0.05 1

10026502 25120000 0 101 1 0.05 2

* Right Boundary Condition Data 

* bound incr type code factor node

10026601 20010000 0 101 1 0.05 1

10026602 20120000 0 101 1 0.05 2

* source mult dmhl dmhr num

10026701 0 0.0 0.0 0.0 2

* Left Additional Boundary Condition Data 

10026800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10026801 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

* Right Additional Boundary Condition Data 

10026900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10026901 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

*n: 4

* nh np geom ssif leftcoord reflood

10030000 10 17 2 1 0.0285 0

* mesh format

10030100 0 1

* intervals radius

10030101 4 0.0291

10030102 8 0.0299

10030103 4 0.0305

* material interval

10030201 2 4

10030202 1 12

10030203 2 16

* rpkf interval

10030301 0.0 4

10030302 1.0 12

10030303 0.0 16

* temp interval

10030401 300.0 17

* Left Boundary Condition Data 

* bound incr type code factor node

10030501 30110000 0 101 1 0.1 1

10030502 30100000 0 101 1 0.1 2

10030503 30090000 0 101 1 0.1 3

10030504 30080000 0 101 1 0.1 4

10030505 30070000 0 101 1 0.1 5

10030506 30060000 0 101 1 0.1 6

10030507 30050000 0 101 1 0.1 7

10030508 30040000 0 101 1 0.1 8

10030509 30030000 0 101 1 0.1 9

10030510 30020000 0 101 1 0.1 10

* Right Boundary Condition Data 

* bound incr type code factor node

10030601 25110000 0 101 1 0.1 1

10030602 25100000 0 101 1 0.1 2

10030603 25090000 0 101 1 0.1 3

10030604 25080000 0 101 1 0.1 4

10030605 25070000 0 101 1 0.1 5

10030606 25060000 0 101 1 0.1 6

10030607 25050000 0 101 1 0.1 7

10030608 25040000 0 101 1 0.1 8

10030609 25030000 0 101 1 0.1 9

10030610 25020000 0 101 1 0.1 10

* source mult dmhl dmhr num

10030701 1000 0.018878743 0.0 0.0 1

10030702 1000 0.02639017 0.0 0.0 2

10030703 1000 0.03176362 0.0 0.0 3

10030704 1000 0.034563769 0.0 0.0 5

10030705 1000 0.03176362 0.0 0.0 6

10030706 1000 0.02639017 0.0 0.0 7

10030707 1000 0.018878743 0.0 0.0 8

10030708 1000 9.837876e-3 0.0 0.0 9

10030709 1000 4.969519e-3 0.0 0.0 10

* Left Additional Boundary Condition Data 

10030800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10030801 9.784e-3 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* Right Additional Boundary Condition Data 

10030900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10030901 0.01083 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* nh np geom ssif leftcoord reflood

10031000 2 7 2 1 0.0285 0

* mesh format

10031100 0 1

* intervals radius

10031101 6 0.0305

* material interval

10031201 2 6

* rpkf interval

10031301 0.0 6

* temp interval

10031401 300.0 7

* Left Boundary Condition Data 

* bound incr type code factor node

10031501 30010000 0 101 1 0.05 1

10031502 30120000 0 101 1 0.05 2

* Right Boundary Condition Data 

* bound incr type code factor node

10031601 25010000 0 101 1 0.05 1

10031602 25120000 0 101 1 0.05 2

* source mult dmhl dmhr num

10031701 0 0.0 0.0 0.0 2

* Left Additional Boundary Condition Data 

10031800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10031801 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

* Right Additional Boundary Condition Data 

10031900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10031901 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

*n: 3

* nh np geom ssif leftcoord reflood

10050000 10 17 2 1 0.024 0

* mesh format

10050100 0 1

* intervals radius

10050101 4 0.0246

10050102 8 0.0254

10050103 4 0.026

* material interval

10050201 2 4

10050202 1 12

10050203 2 16

* rpkf interval

10050301 0.0 4

10050302 1.0 12

10050303 0.0 16

* temp interval

10050401 300.0 17

* Left Boundary Condition Data 

* bound incr type code factor node

10050501 50020000 0 101 1 0.1 1

10050502 50030000 0 101 1 0.1 2

10050503 50040000 0 101 1 0.1 3

10050504 50050000 0 101 1 0.1 4

10050505 50060000 0 101 1 0.1 5

10050506 50070000 0 101 1 0.1 6

10050507 50080000 0 101 1 0.1 7

10050508 50090000 0 101 1 0.1 8

10050509 50100000 0 101 1 0.1 9

10050510 50110000 0 101 1 0.1 10

* Right Boundary Condition Data 

* bound incr type code factor node
B - 13

10050601 30110000 0 101 1 0.1 1

10050602 30100000 0 101 1 0.1 2

10050603 30090000 0 101 1 0.1 3

10050604 30080000 0 101 1 0.1 4

10050605 30070000 0 101 1 0.1 5

10050606 30060000 0 101 1 0.1 6

10050607 30050000 0 101 1 0.1 7

10050608 30040000 0 101 1 0.1 8

10050609 30030000 0 101 1 0.1 9

10050610 30020000 0 101 1 0.1 10

* source mult dmhl dmhr num

10050701 1000 0.014357363 0.0 0.0 1

10050702 1000 0.020069835 0.0 0.0 2

10050703 1000 0.024156366 0.0 0.0 3

10050704 1000 0.026285892 0.0 0.0 5

10050705 1000 0.024156366 0.0 0.0 6

10050706 1000 0.020069835 0.0 0.0 7

10050707 1000 0.014357363 0.0 0.0 8

10050708 1000 7.481746e-3 0.0 0.0 9

10050709 1000 3.77934e-3 0.0 0.0 10

* Left Additional Boundary Condition Data 

10050800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10050801 9.742e-3 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* Right Additional Boundary Condition Data 

10050900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10050901 0.011028 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* nh np geom ssif leftcoord reflood

10051000 2 7 2 1 0.024 0

* mesh format

10051100 0 1

* intervals radius

10051101 6 0.026

* material interval

10051201 2 6

* rpkf interval

10051301 0.0 6

* temp interval

10051401 300.0 7

* Left Boundary Condition Data 

* bound incr type code factor node

10051501 50010000 0 101 1 0.05 1

10051502 50120000 0 101 1 0.05 2

* Right Boundary Condition Data 

* bound incr type code factor node

10051601 30120000 0 101 1 0.05 1

10051602 30010000 0 101 1 0.05 2

* source mult dmhl dmhr num

10051701 0 0.0 0.0 0.0 2

* Left Additional Boundary Condition Data 

10051800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10051801 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

* Right Additional Boundary Condition Data 

10051900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10051901 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

*n: 2

* nh np geom ssif leftcoord reflood

10055000 10 17 2 1 0.0195 0

* mesh format

10055100 0 1

* intervals radius

10055101 4 0.0201

10055102 8 0.0209

10055103 4 0.0215

* material interval

10055201 2 4

10055202 1 12

10055203 2 16

* rpkf interval

10055301 0.0 4

10055302 1.0 12

10055303 0.0 16

* temp interval

10055401 300.0 17

* Left Boundary Condition Data 

* bound incr type code factor node

10055501 55020000 0 101 1 0.1 1

10055502 55030000 0 101 1 0.1 2

10055503 55040000 0 101 1 0.1 3

10055504 55050000 0 101 1 0.1 4

10055505 55060000 0 101 1 0.1 5

10055506 55070000 0 101 1 0.1 6

10055507 55080000 0 101 1 0.1 7

10055508 55090000 0 101 1 0.1 8

10055509 55100000 0 101 1 0.1 9

10055510 55110000 0 101 1 0.1 10

* Right Boundary Condition Data 

* bound incr type code factor node

10055601 50020000 0 101 1 0.1 1

10055602 50030000 0 101 1 0.1 2

10055603 50040000 0 101 1 0.1 3

10055604 50050000 0 101 1 0.1 4

10055605 50060000 0 101 1 0.1 5

10055606 50070000 0 101 1 0.1 6

10055607 50080000 0 101 1 0.1 7

10055608 50090000 0 101 1 0.1 8

10055609 50100000 0 101 1 0.1 9

10055610 50110000 0 101 1 0.1 10

* source mult dmhl dmhr num

10055701 1000 0.011184465 0.0 0.0 1

10055702 1000 0.015634512 0.0 0.0 2

10055703 1000 0.018817943 0.0 0.0 3

10055704 1000 0.020476855 0.0 0.0 5

10055705 1000 0.018817943 0.0 0.0 6

10055706 1000 0.015634512 0.0 0.0 7

10055707 1000 0.011184465 0.0 0.0 8

10055708 1000 5.828322e-3 0.0 0.0 9

10055709 1000 2.944127e-3 0.0 0.0 10

* Left Additional Boundary Condition Data 

10055800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10055801 0.09676 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* Right Additional Boundary Condition Data 

10055900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10055901 0.011343 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* nh np geom ssif leftcoord reflood

10056000 2 7 2 1 0.0195 0

* mesh format

10056100 0 1

* intervals radius

10056101 6 0.0215

* material interval

10056201 2 6

* rpkf interval

10056301 0.0 6

* temp interval

10056401 300.0 7

* Left Boundary Condition Data 

* bound incr type code factor node

10056501 55120000 0 101 1 0.05 1

10056502 55010000 0 101 1 0.05 2

* Right Boundary Condition Data 

* bound incr type code factor node

10056601 50120000 0 101 1 0.05 1

10056602 50010000 0 101 1 0.05 2

* source mult dmhl dmhr num

10056701 0 0.0 0.0 0.0 2

* Left Additional Boundary Condition Data 

10056800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10056801 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

* Right Additional Boundary Condition Data 

10056900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10056901 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

*n: 1

* nh np geom ssif leftcoord reflood

10060000 10 17 2 1 0.015 0

* mesh format

10060100 0 1

* intervals radius

10060101 4 0.0156
B - 14

10060102 8 0.0164

10060103 4 0.017

* material interval

10060201 2 4

10060202 1 12

10060203 2 16

* rpkf interval

10060301 0.0 4

10060302 1.0 12

10060303 0.0 16

* temp interval

10060401 300.0 17

* Left Boundary Condition Data 

* bound incr type code factor node

10060501 60020000 0 101 1 0.1 1

10060502 60030000 0 101 1 0.1 2

10060503 60040000 0 101 1 0.1 3

10060504 60050000 0 101 1 0.1 4

10060505 60060000 0 101 1 0.1 5

10060506 60070000 0 101 1 0.1 6

10060507 60080000 0 101 1 0.1 7

10060508 60090000 0 101 1 0.1 8

10060509 60100000 0 101 1 0.1 9

10060510 60110000 0 101 1 0.1 10

* Right Boundary Condition Data 

* bound incr type code factor node

10060601 55020000 0 101 1 0.1 1

10060602 55030000 0 101 1 0.1 2

10060603 55040000 0 101 1 0.1 3

10060604 55050000 0 101 1 0.1 4

10060605 55060000 0 101 1 0.1 5

10060606 55070000 0 101 1 0.1 6

10060607 55080000 0 101 1 0.1 7

10060608 55090000 0 101 1 0.1 8

10060609 55100000 0 101 1 0.1 9

10060610 55110000 0 101 1 0.1 10

* source mult dmhl dmhr num

10060701 1000 8.72547e-3 0.0 0.0 1

10060702 1000 0.012197137 0.0 0.0 2

10060703 1000 0.014680665 0.0 0.0 3

10060704 1000 0.015974851 0.0 0.0 5

10060705 1000 0.014680665 0.0 0.0 6

10060706 1000 0.012197137 0.0 0.0 7

10060707 1000 8.72547e-3 0.0 0.0 8

10060708 1000 4.546918e-3 0.0 0.0 9

10060709 1000 2.296836e-3 0.0 0.0 10

* Left Additional Boundary Condition Data 

10060800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10060801 9.563e-3 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* Right Additional Boundary Condition Data 

10060900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10060901 0.011926 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

* nh np geom ssif leftcoord reflood

10061000 2 7 2 1 0.015 0

* mesh format

10061100 0 1

* intervals radius

10061101 6 0.017

* material interval

10061201 2 6

* rpkf interval

10061301 0.0 6

* temp interval

10061401 300.0 7

* Left Boundary Condition Data 

* bound incr type code factor node

10061501 60120000 0 101 1 0.05 1

10061502 60010000 0 101 1 0.05 2

* Right Boundary Condition Data 

* bound incr type code factor node

10061601 55120000 0 101 1 0.05 1

10061602 55010000 0 101 1 0.05 2

* source mult dmhl dmhr num

10061701 0 0.0 0.0 0.0 2

* Left Additional Boundary Condition Data 

10061800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10061801 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

* Right Additional Boundary Condition Data 

10061900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10061901 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 2

*n: 0

* nh np geom ssif leftcoord reflood

10080000 12 17 2 1 0.0105 0

* mesh format

10080100 0 1

* intervals radius

10080101 16 0.0125

* material interval

10080201 3 16

* rpkf interval

10080301 0.0 16

* temp interval

10080401 300.0 17

* Left Boundary Condition Data 

* bound incr type code factor node

10080501 80020000 0 101 1 0.1 1

10080502 80030000 0 101 1 0.1 2

10080503 80040000 0 101 1 0.1 3

10080504 80050000 0 101 1 0.1 4

10080505 80060000 0 101 1 0.1 5

10080506 80070000 0 101 1 0.1 6

10080507 80080000 0 101 1 0.1 7

10080508 80090000 0 101 1 0.1 8

10080509 80100000 0 101 1 0.1 9

10080510 80110000 0 101 1 0.1 10

10080511 80010000 0 101 1 0.05 11

10080512 80120000 0 101 1 0.05 12

* Right Boundary Condition Data 

* bound incr type code factor node

10080601 60020000 0 101 1 0.1 1

10080602 60030000 0 101 1 0.1 2

10080603 60040000 0 101 1 0.1 3

10080604 60050000 0 101 1 0.1 4

10080605 60060000 0 101 1 0.1 5

10080606 60070000 0 101 1 0.1 6

10080607 60080000 0 101 1 0.1 7

10080608 60090000 0 101 1 0.1 8

10080609 60100000 0 101 1 0.1 9

10080610 60110000 0 101 1 0.1 10

10080611 60010000 0 101 1 0.05 11

10080612 60120000 0 101 1 0.05 12

* source mult dmhl dmhr num

10080701 0 0.0 0.0 0.0 12

* Left Additional Boundary Condition Data 

10080800 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10080801 9.563e-3 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

10080802 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 12

* Right Additional Boundary Condition Data 

10080900 0

* hthd hlf hlr gslf gslr glcf glcr lbf node

10080901 0.011926 10.0 10.0 0.0 0.0 0.0 0.0 1.0 10

10080902 0.0 10.0 10.0 0.0 0.0 0.0 0.0 1.0 12

****************************** Point Kinetics 

****************************** type feedback

30000000 point separabl

* decay power react dnf

30000001 gamma-ac 1.98e6 0.0 45.03311

* control

30000011 2 * General Table 2 (PK + PAR)

30000012 3 * General Table 3 (PB)

30000013 4 * General Table 4 (Reactivity_Slow)

30000014 5 * General Table 5 (Reactivity_Fast)

.



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-0422 Transient Analysis of the Research Reactor MARIA MC 

Fuel Elements Using RELAP5 Mod 3.3