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German Contribution to Item 2 of the Agenda “Status of ... - IAEA

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Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

<strong>German</strong> <strong>Contribution</strong> <strong>to</strong> <strong>Item</strong> 2 <strong>of</strong> <strong>the</strong> <strong>Agenda</strong><br />

<strong>“Status</strong> <strong>of</strong> National & International GCR<br />

Programs”<br />

H.-J. Allelein et al.


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Content<br />

I<br />

General Situation <strong>of</strong> Nuclear Energy in <strong>German</strong>y<br />

II<br />

HTR activities in <strong>the</strong> Research Center Jülich and at<br />

LRST Aachen University<br />

III<br />

Outlook<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

2


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

I<br />

General Situation <strong>of</strong> Nuclear Energy in<br />

<strong>German</strong>y<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

3


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

General Situation <strong>of</strong> Nuclear Energy in <strong>German</strong>y (1)<br />

• Decision in Oct. 2010 for lifetime extension<br />

8 years for seven plants censtructed before 1980 D<br />

14 years for ten younger plants<br />

• After Fukushima it was decided in June 2011 <strong>to</strong> shutdown<br />

<strong>the</strong>se seven older plants plus Krümmel NPP.<br />

The o<strong>the</strong>r nine plants have <strong>to</strong> phase out, so that <strong>the</strong> last one<br />

will be shutdown in 2022.<br />

In general <strong>the</strong> situation for nuclear activities in <strong>German</strong>y is<br />

difficult, in particular for HTR related ones.<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

4


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

General Situation <strong>of</strong> Nuclear Energy in <strong>German</strong>y (2)<br />

• Following <strong>the</strong> actual <strong>German</strong> policy <strong>the</strong> remaining activities are<br />

focused on<br />

nuclear waste<br />

conservation <strong>of</strong> know-how and competence<br />

national R&D programs funded by <strong>the</strong> two Federal Ministries <strong>of</strong><br />

Economics and Technology and <strong>of</strong> Education and Research,<br />

respectively<br />

with reference <strong>to</strong> HTR<br />

o<br />

o<br />

analytical activities (3d fluid mechanics, core behavior)<br />

experimental activities (fluid mechanics, dust behavior,<br />

graphite corrosion)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

5


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

General Situation <strong>of</strong> Nuclear Energy in <strong>German</strong>y (3)<br />

National projects or activities as parts <strong>of</strong> such ones<br />

• GRS, IKE Stuttgart University<br />

(anal.: fluid mechanics, core behavior)<br />

• LRST Aachen University and Technical University Dresden<br />

(exp. and anal.: investigations <strong>of</strong> dust behavior)<br />

• Research Center Jülich (RCJ)<br />

(anal.: fluid mechanics for pebbles and block type in<br />

different scales, core behavior)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

6


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

General Situation <strong>of</strong> Nuclear Energy in <strong>German</strong>y (4)<br />

International activities<br />

• EC Framework Programme (FP)-7<br />

(ARCHER, CARBOWASTE, GoFastR…)<br />

mainly analytical, different <strong>German</strong> partners<br />

• OECD-LOFC Project<br />

(Loss <strong>of</strong> Forced Coolant, Japanese HTTR, GRS and RCJ)<br />

• Co-operation between INET and RCJ<br />

• Working group on rework <strong>of</strong> AVR operation<br />

(caused by regional policy and RCJ board)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

7


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

II<br />

HTR activities in <strong>the</strong> Research Center<br />

Jülich and at LRST Aachen University<br />

Test facilities INDEX and NACOK2<br />

H.-J. Allelein<br />

New Models for fission product<br />

release, fuel management and dust<br />

issues<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

8


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Scope <strong>of</strong> Activities<br />

Small scale<br />

experiments<br />

INDEX<br />

(high numbers)<br />

Integral experiments<br />

NACOK 2<br />

(detailed<br />

investigation)<br />

Code validation<br />

CFX<br />

(fluid mechanics<br />

HTRs)<br />

Code validation<br />

HCP<br />

(fluid mechanics<br />

HTRs)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

9


h~300<br />

105 mm<br />

Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

INDEX (small scale experiment)<br />

Laser<br />

IR camera<br />

TC<br />

Ø 95<br />

• Flow channel made <strong>of</strong> fused glass<br />

• Quadratic cross section (66x66mm)<br />

Induction coil<br />

(water cooled)<br />

camera<br />

Inlet <strong>of</strong> cooling water<br />

• Induction coil designed for 200g graphite<br />

• max. temperature pebble 1200°C<br />

pyrometer<br />

graphite sample<br />

induktive heatet<br />

up <strong>to</strong> 1200°C<br />

glas<br />

pyrometer<br />

• max. heating rate pebble 500°C/min<br />

Outlet <strong>of</strong> cooling water<br />

• First set up with single sphere (D=60mm)<br />

a=67<br />

• Later pebble bed, block elements<br />

flow chanel<br />

• TC, pyrometer, IR camera<br />

• Gas analytics (He, O 2 , CO 2 , CO)<br />

• Particle Imaging Velocimetry (2D / 3D)<br />

GAS (N2- 21°C)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

10


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

INDEX<br />

First series:<br />

• single pebble<br />

• inductive heated single sphere<br />

• 700, 900, 1000, 1100, 1200°C<br />

• nitrogen flow 22 l/min<br />

• 2D PIV (classic)<br />

• flow field above <strong>the</strong> pebble<br />

• sequence <strong>of</strong> 200 pictures<br />

• measurements done in cold and hot state<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

11


max. pebble surface temperature / °C<br />

Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

CFX: INDEX cool down experiment<br />

Temperature<br />

970<br />

800<br />

700<br />

Experiment<br />

Best Estimate<br />

Fine Grid<br />

600<br />

400<br />

[K]<br />

500<br />

400<br />

300<br />

200<br />

0 200 400 600 800 1000 1200<br />

time / s<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

12


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

INDEX<br />

Modifications in progress:<br />

• optimizing setup for dust<br />

experiments<br />

• new fused glass flow channel<br />

• ports for additional instrumentation<br />

(particle measurement by APS,<br />

SMPS)<br />

• new exhaust for particle loaded gas<br />

• moveable induction coil<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

13


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

NACOK2- Set-up Run<br />

• 5 segments (upgradeable)<br />

• ceramic flow channel<br />

• base plate<br />

• one ceramic block with holes<br />

• windows<br />

• simple “chimney” set up<br />

• strait, open gas inlet<br />

• open exhaust<br />

• 24 <strong>the</strong>rmo couples<br />

• ultra sonic flow meter<br />

• 2D PIV<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

14


T [°C]<br />

Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

1400<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Temperatures<br />

TRC Zone 1<br />

TRC Zone 2<br />

1200<br />

TRC Zone 3<br />

TRC Zone 4<br />

TRC Zone 5<br />

1000<br />

Zone 1 solid<br />

Zone 1 Gas<br />

Zone 2 Window<br />

800<br />

Zone 3 Wall<br />

Zone 4 Wall<br />

Zone 5 Wall<br />

600<br />

400<br />

Block center bot<strong>to</strong>m<br />

Block center middle<br />

Block center <strong>to</strong>p<br />

Block edge <strong>to</strong>p<br />

200<br />

0<br />

35 40 45 50 55 60<br />

Dt [h]<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

15


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

NACOK2- Pebble Bed 1000°C<br />

• simple “chimney” set up<br />

• heating rate 30°C/h<br />

• 8 layers <strong>of</strong> ceramic pebbles<br />

• 200 <strong>to</strong>tal with half spheres<br />

• T max = 1000°C (upper pebble layer)<br />

• gas flow variation: 20, 30, 40 m³/h<br />

• four sets <strong>of</strong> PIV measurements at:<br />

1. 20 m³/h, 1000°C (layer 8)<br />

2. 30 m³/h, same furnace temperature<br />

→ T drop<br />

3. 30 m³/h, 1000°C (layer 8)<br />

4. 40 m³/h, 1000°C (layer 8)<br />

• 120 h experimental time<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

16


T [°C]<br />

Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

1200<br />

1100<br />

1000<br />

900<br />

800<br />

Temperatures<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Zone 1 solid<br />

1. Layer (1,1)<br />

1. Layer (2,2)<br />

1. Layer (3,3)<br />

1. Layer (4,4)<br />

1. Layer (5,5)<br />

5. Layer (3,1)<br />

5. Layer (3,3)<br />

8. Layer (3, 3.5)<br />

Zone 2 wall<br />

Zone 3 wall<br />

700<br />

Zone 4 wall<br />

Zone 5 wall<br />

600<br />

500<br />

400<br />

H.-J. Allelein<br />

1 2 3 4<br />

35 40 45 50 55 60 65 70 75<br />

Dt [h]<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

17


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

PIV at 1000°C, flow rate 20m³/h<br />

gas flow<br />

20m³/h<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

18


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

CFX: Simulation <strong>of</strong> <strong>the</strong> 1 st Pebble Experiment<br />

Resulting mass flow<br />

21.7 m³/h<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

19


temperature / °C<br />

Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Transient for <strong>the</strong> 1st NACOK2 test with ceramic pebbles<br />

1200<br />

in air<br />

center <strong>of</strong> <strong>the</strong> <strong>to</strong>p layer<br />

1000<br />

800<br />

600<br />

MGT-3D, but only 2D<br />

MGT-3D simulation (2D-Modell)<br />

Experiment<br />

400<br />

200<br />

max. deviation: 75,07°C<br />

0<br />

11-6-12 0:00 12-6-12 0:00 13-6-12 0:00 14-6-12 0:00 15-6-12 0:00 16-6-12 0:00<br />

time<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

20


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

NACOK2<br />

Modifications in progress:<br />

• optimizing setup for graphite experiments<br />

• gas tight closed system (pneumatic valves<br />

with exhaust gas cooler at outlet)<br />

• gas support N 2 , He, air, CO 2 , gas mixtures<br />

up <strong>to</strong> 50 m³/h<br />

• gas analytics He, O 2 , CO 2 , CO in flow<br />

channel and heating zone<br />

• pressure measurement in every segment<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

21


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

HTR Code Package (HCP)<br />

Objective: "Design, implementation and validation <strong>of</strong> s<strong>of</strong>tware for <strong>the</strong> simulation <strong>of</strong><br />

V/HTRs applying <strong>the</strong> latest programming techniques and standards."<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

22


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

STACY<br />

… Source Term Analysis Code System<br />

SHUFLE … S<strong>of</strong>tware for Handling Universal Fuel<br />

Elements<br />

STAR<br />

… Source Term Aerosol Resuspension<br />

(for graphite dust transport, deposition and<br />

resuspension)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

23


„x“ core passes<br />

Temperature [°C]<br />

Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Former Approach for FP Release Calculation<br />

(Fuel temperature [°C]<br />

HTR-Module, VSOP)<br />

• FRESCO-II: Fission product release calculation for one or several<br />

representative fuel element(s)<br />

• Time averaged release rate <strong>of</strong> sphere is multiplied with <strong>the</strong> <strong>to</strong>tal<br />

number <strong>of</strong> fuel elements <strong>to</strong> determine core release rate<br />

−<br />

−<br />

−<br />

Conservative approach<br />

No spatial distribution <strong>of</strong> fission product release<br />

More detailed calculation method necessary for best estimate<br />

calculations particularly with regard <strong>to</strong> design basis and beyond<br />

design basis accidents<br />

1200<br />

1000<br />

800<br />

600<br />

400<br />

200<br />

0<br />

0 250 500 750 1000 1250<br />

Time [d]<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

24


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Main Principles <strong>of</strong> STACY (1)<br />

• Calculation <strong>of</strong> CP failure fractions and FP release rates <strong>of</strong> a large<br />

number <strong>of</strong> individual tracer pebbles<br />

−<br />

−<br />

Spatially resolved fission product release rates<br />

Best estimate calculation <strong>of</strong> <strong>to</strong>tal release rate from core<br />

• Usage <strong>of</strong> stand-alone codes as an intermediate step:<br />

−<br />

VSOP: neutron flux and fluid temperature distributions<br />

under normal operation conditions<br />

− MGT: accident temperature distributions<br />

• Fuel shuffling is modeled so far after stream tube model in VSOP<br />

(later on SHUFLE will be used)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

25


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Main Principles <strong>of</strong> STACY (2)<br />

• Tracer pebbles are added <strong>to</strong> <strong>the</strong> core according <strong>to</strong> a given distribution with<br />

<strong>the</strong> help <strong>of</strong> a random number genera<strong>to</strong>r<br />

• For each tracer pebble, an individual burnup and radial temperature pr<strong>of</strong>ile<br />

calculation is performed<br />

• Simulation <strong>of</strong> FP release rate and CP damage fraction for each individual<br />

tracer pebble<br />

• Combining results <strong>to</strong> spatially resolved FP release distributions by<br />

determining average release rate <strong>of</strong> tracer pebbles within each region<br />

• FP release <strong>of</strong> tracer pebbles is representative for core in case distribution<br />

<strong>of</strong> tracer elements over core volume is representative<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

26


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Calculation <strong>of</strong> Fission Product Inven<strong>to</strong>ry<br />

• FRESCO-II:<br />

− Relative fission product release calculation with<br />

constant birth rate <strong>of</strong> fission product <strong>of</strong> interest<br />

− Neglecting space dependent neutron fluxes<br />

− Birth rate during accident is neglected<br />

• STACY:<br />

− Coupling <strong>of</strong> STACY with newly developed burnup<br />

code TNT<br />

− Including precise calculation <strong>of</strong> inven<strong>to</strong>ry in fission<br />

product release calculation<br />

− Still condensed birth and removal rate<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

27


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

I-131 Inven<strong>to</strong>ry <strong>of</strong> a Tracer Pebble<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

28


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Spatial distribution <strong>of</strong> I-131 Release Rates<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

29


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Fission Product Release Fractions during DLOFC<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

30


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Comparison <strong>of</strong> STACY and Intera<strong>to</strong>m Results (1)<br />

Equilibrium core: Output power specific release values [Bq/(MW th ∙h)]<br />

Nuclide<br />

STACY<br />

Design<br />

SLIPPER<br />

(Intera<strong>to</strong>m)<br />

STACY<br />

Expected<br />

SLIPPER<br />

(Intera<strong>to</strong>m)<br />

Cs-137 2.7×10 3 5.9×10 4 6.8×10 2 3.0×10 4<br />

I-131 5.1×10 7 3.8×10 6 1.3×10 7 9.5×10 5<br />

1<br />

: N. N. :Aktivitätsfreisetzung und Strahlenexposition bei der HTR-Modul-Kraftwerksanlage Teil I: Bestimmungsgemäßer Betrieb,<br />

HTR-Modul Kraftwerk Konzeptbegutachtungsunterlagen, Band 4, Siemens Intera<strong>to</strong>m, 1987<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

31


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Comparison <strong>of</strong> STACY and Intera<strong>to</strong>m Results (2)<br />

DLOFC: Cumulative relative release fraction <strong>of</strong> core inven<strong>to</strong>ry after 200 h<br />

Design<br />

Expected<br />

Nuclide<br />

STACY<br />

+90°C Nom. temperature +90°C Nom. temperature<br />

FRESCO-I<br />

(Intera<strong>to</strong>m)<br />

STACY<br />

FRESCO-I<br />

(Intera<strong>to</strong>m)<br />

STACY<br />

FRESCO-I<br />

(Intera<strong>to</strong>m)<br />

STACY<br />

FRESCO-I<br />

(Intera<strong>to</strong>m)<br />

Cs-137 2.6x10 -5 8.4x10 -5 4.8x10 -6 8.4x10 -5 7.8x10 -6 5.1x10 -5 6.0x10 -7 9.0x10 -6<br />

I-131 5.3x10 -5 2.9x10 -5 2.1x10 -5 1.2x10 -5 5.0x10 -6 9.1x10 -6 3.2x10 -6 1.1x10 -6<br />

DLOFC …<br />

Depressurized Loss <strong>of</strong> Forced Cooling accident<br />

2<br />

: N. N.: Aktivitätsfreisetzung und Strahlenexposition bei der HTR-Modul-Kraftwerksanlage Teil II: Störfälle,<br />

HTR-Modul Kraftwerk Konzeptbegutachtungsunterlagen, Band 4, Siemens Intera<strong>to</strong>m, 1988<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

32


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Comparison <strong>of</strong> STACY and Intera<strong>to</strong>m Results (3)<br />

STACY results in comparison <strong>to</strong> Intera<strong>to</strong>m results (STACY / Intera<strong>to</strong>m):<br />

Equilibrium core: Output power specific release values [Bq/(MW th ∙h)]<br />

• Iodine-131: Order <strong>of</strong> magnitude higher<br />

• Cesium-137: Fac<strong>to</strong>r <strong>of</strong> 20 lower<br />

(mainly affected by modified modeling and not by revised<br />

difusion coefficient for Sic)<br />

DLOFC: Cumulative relative release fraction <strong>of</strong> core inven<strong>to</strong>ry after 200 h<br />

• Iodine-131: Fac<strong>to</strong>r <strong>of</strong> 2 higher<br />

• Cesium-137: Fac<strong>to</strong>r <strong>of</strong> 3 (design) <strong>to</strong> 6 (expected) lower<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

33


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Summary for STACY<br />

• Original codes have been modernized and merged <strong>to</strong> form one consistent<br />

code module STACY<br />

• STACY has been extended and coupled with <strong>the</strong> code system VSOP and<br />

burn up code TNT <strong>to</strong> enable detailed spatially resolved fission product<br />

release calculations<br />

• Fission product release rate <strong>of</strong> short-living respectively long-living nuclides<br />

are higher respectively lower in comparison <strong>to</strong> former calculation methods<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

34


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Motivation for a New Fuel Shuffling Approach<br />

• Fuel tube model is limited with respect <strong>to</strong> new<br />

functionalities<br />

• Flow tube model requires an additional grid, which<br />

is not preferred in HTR Code Package (HCP)<br />

• More elaborated approaches, like Discrete<br />

Element Method (DEM) are <strong>to</strong>o time consuming for<br />

being used in a multi-physics code package<br />

• New approach is required for HCP<br />

S<strong>of</strong>tware for Handling <strong>of</strong> Universal FueL Elements<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

35


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Requirements for Fuel Shuffling Code<br />

• Fuel management <strong>of</strong> spherical and prismatic block type fuel elements<br />

• 2D/3D-geometry, cartisan and dylindrical coordinates<br />

• Manually and au<strong>to</strong>matically repositioning <strong>of</strong> fuel elements<br />

• XML based input concept (e.g. shuffling scheme)<br />

• Usage <strong>of</strong> HCP data model (e.g. fuel element and mesh object)<br />

• High level <strong>of</strong> source code reusability<br />

• Acceptable simulation time with respect <strong>to</strong> o<strong>the</strong>r code modules<br />

• Extendible on future demands<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

36


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

New Aspects <strong>of</strong> SHUFLE<br />

• Modelling <strong>of</strong> discharge tube<br />

• Differing flow velocities in azimuthal direction<br />

• Space dependent filling fac<strong>to</strong>r / densification <strong>of</strong> pebble bed<br />

• Tracking <strong>of</strong> single batches (multi fuel pass fuel strategy)<br />

• Simulation <strong>of</strong> conical pebble heap(s)<br />

• More precise modelling <strong>of</strong> stagnant zones<br />

1030°C<br />

900°C<br />

935°C<br />

Fig.: Fuel temperature distribution [2]<br />

Fig.: Stagnant zones [1]<br />

[1] Yang, X.: Experimental Investigation on Feasibility <strong>of</strong> Two-Region-Designed Pebble-Bed High-Temperature Gas-Cooled Reac<strong>to</strong>r, INET, 2008<br />

[2] Verfondern, K.: Numerische Untersuchung der 3-dimensionalen stationären Temperatur- und Strömungsverteilung im Core eines Kugelhaufen-Hochtemperaturreak<strong>to</strong>rs, 1984<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

37


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Pebble Flow in SHUFLE<br />

• The laminar flow paths <strong>of</strong> fuel pebbles in SHUFLE are simulated by propagating<br />

smaller voids which are created at <strong>the</strong> core bot<strong>to</strong>m when discharging pebbles<br />

• SHUFLE processes flow lines measured experimentally <strong>of</strong> created by a code based<br />

on real physics (e.g. DEM)<br />

• Main purpose is <strong>to</strong> display fuel movement in larger framework (e.g. HCP)<br />

Fig.: Measured flow paths [1]<br />

Fig.: Silo drainage [2]<br />

[1] Yang, X.: Experimental Investigation on Feasibility <strong>of</strong> Two-Region-Designed Pebble-Bed High-Temperature Gas-Cooled Reac<strong>to</strong>r, INET, 2008<br />

[2] Kamrin K., Rycr<strong>of</strong> C., Bazant M., The s<strong>to</strong>chastic flow rule: a multi-scale model for granular plasticity, MIT. Cambridge, 2007<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

38


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Validation Setup<br />

• ANABEK test facility (Siemens-Intera<strong>to</strong>m)<br />

• Pebble bed surface is covered with marked test spheres<br />

• Pebble bed is shuffled as long as marked spheres are within <strong>the</strong> vessel<br />

• Result: residence time distribution (RTD)<br />

„test spheres“<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

39


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Simulation Results (Residence Time Distribution)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

40


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Summary for SHUFLE<br />

• The HTR Code Package (HCP) requires a detailed fuel shuffling approach<br />

based on its data model => SHUFLE<br />

• The new code SHUFLE is able <strong>to</strong> fill <strong>the</strong> gap between sophisticated codes<br />

(e.g. DEM) and rudimentary models (e.g. stream tube model)<br />

• It was shown that residence time distributions from <strong>the</strong> ANABEK test<br />

facility were accurately simulated by SHUFLE<br />

• SHUFLE will become part <strong>of</strong> <strong>the</strong> HCP<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

41


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Implementation <strong>of</strong> dust module STAR<br />

Modelling <strong>of</strong> Staub- (dust):<br />

Transport<br />

• convective dust exchange between meshes<br />

• interaction <strong>of</strong> dust concentration with deposition and resuspension<br />

Ablagerung (deposition)<br />

• implementation <strong>of</strong> <strong>the</strong>oretical / semi-empirical correlations<br />

• modeling <strong>of</strong> dust behavior on <strong>the</strong> surface for adhesive forces<br />

Resuspension<br />

• implementation <strong>of</strong> <strong>the</strong> quasi-static Rock‘n Roll model<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

42


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

STAR<br />

• <strong>the</strong> STAR code was developed for <strong>the</strong> simulation <strong>of</strong> dust behavior in HTR<br />

• first application for an estimate <strong>of</strong> <strong>the</strong> source term due <strong>to</strong> dust for<br />

depressurization <strong>of</strong> <strong>the</strong> HTR-Module<br />

• rough assessment <strong>of</strong> activity released with <strong>the</strong> INES scale:<br />

• Level 3 event for design basis accident (DBA)<br />

• Level 4 event (unfavorable assumptions) for beyond DBA<br />

Future work:<br />

• improved simulation <strong>of</strong> dust in confinement (project ARCHER)<br />

• fur<strong>the</strong>r validation / improvement <strong>of</strong> STAR with focus on conditions<br />

representative for HTR (project TARGET)<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

43


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

III<br />

Outlook<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

44


Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />

Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />

Institut für Energie- und Klimaforschung<br />

Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />

Current <strong>German</strong> activities funded until 2015<br />

Main objectives <strong>to</strong> be achieved until <strong>the</strong>n<br />

• availability <strong>of</strong> <strong>the</strong> first HTR Code Package (HCP) version<br />

• extension <strong>of</strong> <strong>the</strong> experimental data base for fluid mechanics and<br />

graphite dust behaviour, e.g. for MGT-3D<br />

• capability <strong>of</strong> performing predictive calculations for block-type fuel<br />

HTR<br />

H.-J. Allelein<br />

TWG-GCR-23<br />

March 5-7, 2013, Vienna<br />

45

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