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