STACY Code and its Application to the HTR-Module and HTTR
STACY Code and its Application to the HTR-Module and HTTR
STACY Code and its Application to the HTR-Module and HTTR
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meinschaft<br />
Mitglied der Helmholtz-Gem<br />
Development of an Integrated Fission Product Release<br />
<strong>and</strong> Transport <strong>Code</strong> for Spatially Resolved Full-Core<br />
Calculations of V/<strong>HTR</strong>s<br />
A. Xhonneux<br />
Forschungszentrum Jülich, Germany<br />
Technical Meeting on Re-evaluation of Maximum Operating Temperatures<br />
g p g p<br />
<strong>and</strong> Accident Conditions for <strong>HTR</strong> Fuel <strong>and</strong> Structural Materials<br />
IAEA Headquarters,Vienna, June 10-12 2013
Overview<br />
• Overview of Fission Product <strong>Code</strong>s at FZJ<br />
• Introduction <strong>to</strong> <strong>STACY</strong><br />
• Exemplary results for <strong>HTR</strong>-<strong>Module</strong><br />
• Exemplary results for <strong>HTTR</strong><br />
• Summary <strong>and</strong> outlook<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
2<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Overview<br />
• Overview of Fission Product <strong>Code</strong>s at FZJ<br />
• Introduction <strong>to</strong> <strong>STACY</strong><br />
• Exemplary results for <strong>HTR</strong>-<strong>Module</strong><br />
• Exemplary results for <strong>HTTR</strong><br />
• Summary <strong>and</strong> outlook<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
3<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Overview of Fission Product <strong>Code</strong>s at FZJ<br />
FP release rate from one FE<br />
(NOC <strong>and</strong> accident Conditions)<br />
•Fickean diffusion of FPs<br />
in defective <strong>and</strong> intact<br />
CPs / FEs<br />
•Recoil<br />
•SiC layer thinning<br />
Release from FEs <strong>and</strong><br />
transport under<br />
accident conditions<br />
•FP transport in core<br />
due <strong>to</strong> convection<br />
•Deposition on reflec<strong>to</strong>r<br />
surfaces<br />
Fuel Performance<br />
• CP damage fractions<br />
• SiC layer thinning<br />
due <strong>to</strong> <strong>the</strong>rmal<br />
decompostion<br />
o<br />
Deposition / penetration<br />
metallic surfaces<br />
(primary loop)<br />
• Some features have been implemented multiple times in <strong>the</strong> separate codes<br />
• Not complete <strong>to</strong> describe all phenomena under NOC <strong>and</strong> accident conditions<br />
<strong>STACY</strong>: Source Term Analysis l i <strong>Code</strong> d System<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
4<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Former Approach for FP Release Calculation<br />
• FRESCO-II: Fission product release calculation for one or<br />
several representative fuel element(s)<br />
• Time averaged release rate of sphere is multiplied with <strong>the</strong><br />
<strong>to</strong>tal number of fuel elements <strong>to</strong> determine core release rate<br />
„x“ cor re passes<br />
‣ Conservative approach<br />
‣ No spatial distribution of fission product release<br />
‣ More detailed calculation method necessary<br />
(Fuel temperature [°C]<br />
<strong>HTR</strong>-<strong>Module</strong>, VSOP)<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
5<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Overview<br />
• Overview of Fission Product <strong>Code</strong>s at FZJ<br />
• Introduction <strong>to</strong> <strong>STACY</strong><br />
• Exemplary results for <strong>HTR</strong>-<strong>Module</strong><br />
• Exemplary results for <strong>HTTR</strong><br />
• Summary <strong>and</strong> outlook<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
6<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Main Principles of <strong>STACY</strong><br />
• Calculation of CP failure fractions <strong>and</strong> FP release rates for a large number<br />
of individual tracer pebbles<br />
‣ Spatially resolved fission product release rates<br />
‣ More precise (less conservative) calculation of <strong>to</strong>tal release rate<br />
• Usage of st<strong>and</strong>-alone codes as an intermediate step:<br />
• VSOP: neutron flux <strong>and</strong> fluid temperature distributions under NOC<br />
• MGT: accident temperature distributions<br />
• Fuel shuffling is modelled so far after stream tube model in VSOP<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
7<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Main Principles of <strong>STACY</strong><br />
• Tracer pebbles are added <strong>to</strong> <strong>the</strong> core according <strong>to</strong> a given<br />
distribution with <strong>the</strong> help of a r<strong>and</strong>om number genera<strong>to</strong>r<br />
• For each tracer pebble, an individual burnup <strong>and</strong> radial temperature<br />
profile calculation is performed<br />
• Simulation of FP release rate <strong>and</strong> CP damage fraction for each<br />
individual tracer pebble<br />
• Combining results <strong>to</strong> spatially resolved FP release distributions by<br />
determining average release rate of tracer pebbles within each region<br />
• FP release of tracer pebbles is representative for core in case<br />
distribution of tracer elements over core volume is representative<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
8<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Former Fuel Shuffling Scheme in VSOP<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
9<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Influence of Fuel Mixing on Burnup<br />
10<br />
9<br />
8<br />
7<br />
A]<br />
Burn nup [% FIM<br />
6<br />
5<br />
4<br />
3<br />
2<br />
1<br />
0<br />
Channel 1<br />
Channel 2<br />
Channel 3<br />
Channel 4<br />
Burnup Target<br />
15 x Channel 1<br />
15 x Channel 4<br />
1 3 5 7 9 11 13 15<br />
Number of completed core passes<br />
• In comparison <strong>to</strong> “VSOP batches”, tracer pebbles are not mixed<br />
• Tracer pebble is loaded <strong>to</strong> final s<strong>to</strong>rage if burnup target is<br />
reached, not after a predefined number of core passes<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
10<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Screenshot of Tracer Pebbles within Eq. Core<br />
• 4,500 tracer fuel elements<br />
• Volumetric density of tracer fuel<br />
elements is constant<br />
• Colours indicate core pass number<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
11<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Calculation of Fission Product Inven<strong>to</strong>ry<br />
• FRESCO-II:<br />
• Relative fission product release calculation with<br />
constant birth rate of fission product of interest<br />
• Neglecting space dependent d neutron fluxes<br />
• Birth rate during accident is neglected<br />
• <strong>STACY</strong>:<br />
• Coupling of <strong>STACY</strong> with newly developed burnup<br />
code TNT<br />
• Including precise calculation of inven<strong>to</strong>ry in fission<br />
product release calculation<br />
• Still condensed birth <strong>and</strong> removal rate<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
12<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
I-131 Inven<strong>to</strong>ry of a Tracer Pebble<br />
core pass<br />
1.8<br />
1 2 3 4 5 6 7 8 9 10 11 12 13 14 15<br />
en<strong>to</strong>ry<br />
Relative iod dine-131 inv<br />
1.6<br />
1.4<br />
1.2<br />
1.0<br />
0.8<br />
0.6<br />
0.4<br />
0.2<br />
0.0<br />
0 100 200 300 400 500 600 700 800 900 1000<br />
Irradiation time [EFPD]<br />
Inven<strong>to</strong>ry, Q = var., TNT<br />
Inven<strong>to</strong>ry, Q = const<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
13<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
I-131 Release Rate of a Tracer Pebble<br />
core pass 1 2 3 4 5 1 2 3 4 5<br />
1.8<br />
3.0E-12 30<br />
Relative iod dine-131 inve en<strong>to</strong>ry<br />
1.6<br />
1.4<br />
1.2<br />
1.0<br />
0.8<br />
0.6<br />
0.4<br />
0.2<br />
[mol/s]<br />
release rate<br />
Iodine 131<br />
2.5E-12<br />
2.0E-12<br />
1.5E-12<br />
1.0E-12<br />
5.0E-13<br />
0.0<br />
0 100 200 300<br />
0.0E+00<br />
0 100 200 300<br />
Irradiation time [EFPD]<br />
Irradiation time [EFPD]<br />
Inven<strong>to</strong>ry, Q = var., TNT<br />
Inven<strong>to</strong>ry, Q = const<br />
Rel. Rate = f(t), 15x inner, Q = var., TNT<br />
Rel. Rate = f(t), 15x inner, Q = const<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
14<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Overview<br />
• Overview of Fission Product <strong>Code</strong>s at FZJ<br />
• Introduction <strong>to</strong> <strong>STACY</strong><br />
• Exemplary results for <strong>HTR</strong>-<strong>Module</strong><br />
• Exemplary results for <strong>HTTR</strong><br />
• Summary <strong>and</strong> outlook<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
15<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Intera<strong>to</strong>m Safety Analysis of <strong>HTR</strong>-<strong>Module</strong> (1)<br />
• Normal operating conditions<br />
• FP release calculation of one representative<br />
fuel element<br />
• <strong>Code</strong>s being applied:<br />
‣ SLIPPER for condensable fission i products<br />
(cesium, strontium, silver species)<br />
‣ STADIF for noble gases <strong>and</strong> iodine species<br />
• Accident conditions<br />
• Rudimentary calculation of fission product<br />
inven<strong>to</strong>ry distribution at start of <strong>the</strong> accident<br />
• <strong>Code</strong> being applied:<br />
‣ FRESCO-I for all nuclides<br />
(e.g. cesium, strontium, silver <strong>and</strong> iodine species)<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
16<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Intera<strong>to</strong>m Safety Analysis of <strong>HTR</strong>-<strong>Module</strong> (2)<br />
• <strong>Application</strong> of so-called Trumpet Curve for coated particle failure fraction<br />
1.0E-03<br />
Co oated particle<br />
failure frac ction<br />
1.0E-04<br />
Fresh fuel element<br />
Fuel element (50% target burnup)<br />
Fuel element (100% target burnup)<br />
1.0E-05<br />
1000 1100 1200 1300 1400 1500 1600<br />
Fuel temperature [°C]<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
17<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Comparison of Main Parameters<br />
• Neutron flux <strong>and</strong> fuel temperature distribution<br />
in good agreement<br />
• Influence of cone modeling <strong>and</strong> realistic pebble flow<br />
pattern on parameters negligible<br />
fur<strong>the</strong>r use of model without cone <strong>and</strong> parallel<br />
pebble flow<br />
VSOP model of <strong>HTR</strong>-<strong>Module</strong> incl. cone<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
18<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Fission Product Release Fractions during DLOFC<br />
1.0E-04<br />
10E-05<br />
1.0E 05<br />
Re<br />
elative releas<br />
se fraction<br />
1.0E-06<br />
1.0E-07<br />
1.0E-08<br />
08<br />
FRESCO-I<br />
(Intera<strong>to</strong>m)<br />
<strong>STACY</strong><br />
1.0E-09<br />
1.0E-10<br />
0 20 40 60 80 100 120 140 160 180 200<br />
Accident time [h]<br />
FRESCO-I, Cs-137 FRESCO-I, I-131 FRESCO-I, Sr-90<br />
FRESCO-I, Cs-137 FRESCO-I, I-131 FRESCO-I, Sr-90<br />
<strong>STACY</strong>, Cs-137 <strong>STACY</strong>, I-131 <strong>STACY</strong>, Sr-90<br />
1: N. N.: Aktivitätsfreisetzung und Strahlenexposition bei der <strong>HTR</strong>-Modul-Kraftwerksanlage Teil II: Störfälle,<br />
<strong>HTR</strong>-Modul Kraftwerk Konzeptbegutachtungsunterlagen, B<strong>and</strong> 4, Siemens Intera<strong>to</strong>m, 1988<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
19<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Comparison of <strong>STACY</strong> <strong>and</strong> Intera<strong>to</strong>m Results<br />
Equilibrium core: Output power specific release values [Bq/(MW th·h)]<br />
Design<br />
Nuclide <strong>STACY</strong> SLIPPER<br />
(Intera<strong>to</strong>m)<br />
<strong>STACY</strong><br />
Expected<br />
SLIPPER<br />
(Intera<strong>to</strong>m)<br />
Cs‐137 2.67×10 3 5.9×10 4 6.76×10 2 3.0×10 4<br />
I‐131 51×10 5.1×10 7 38×10 3.8×10 6 13×10 1.3×10 7 95×10 9.5×10 5<br />
DLOFC: Cumulative relative release fraction of core inven<strong>to</strong>ry after 200 h<br />
Design<br />
Expected<br />
Nuclide<br />
+90°C Nom. temperature +90°C Nom. temperature<br />
<strong>STACY</strong> FRESCO‐I <strong>STACY</strong> FRESCO‐I <strong>STACY</strong> FRESCO‐I <strong>STACY</strong> FRESCO‐I<br />
(Intera<strong>to</strong>m)<br />
(Intera<strong>to</strong>m)<br />
(Intera<strong>to</strong>m)<br />
(Intera<strong>to</strong>m)<br />
Cs‐137 2.62x10 ‐5 8.44x10 ‐5 4.76x10 ‐6 8.44x10 ‐5 7.81x10 ‐6 5.09x10 ‐5 6.01x10 ‐7 8.98x10 ‐6<br />
I‐131 5.31x10 ‐55 2.86x10 ‐55 2.05x10 ‐55 1.16x1016x10 ‐55 4.96x10 ‐66 9.13x10 ‐66 3.24x10 ‐66 1.12x1012x10 ‐66<br />
1<br />
: N. N. :Aktivitätsfreisetzung und Strahlenexposition bei der <strong>HTR</strong>-Modul-Kraftwerksanlage Teil I: Bestimmungsgemäßer Betrieb,<br />
<strong>HTR</strong>-Modul Kraftwerk Konzeptbegutachtungsunterlagen, B<strong>and</strong> 4, Siemens Intera<strong>to</strong>m, 1987<br />
2<br />
: N. N.: Aktivitätsfreisetzung und Strahlenexposition bei der <strong>HTR</strong>-Modul-Kraftwerksanlage Teil II: Störfälle,<br />
<strong>HTR</strong>-Modul Kraftwerk Konzeptbegutachtungsunterlagen, B<strong>and</strong> 4, Siemens Intera<strong>to</strong>m, 1988<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
20<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Comparison of <strong>STACY</strong> <strong>and</strong> Intera<strong>to</strong>m Results<br />
<strong>STACY</strong> results in comparison <strong>to</strong> Intera<strong>to</strong>m results (<strong>STACY</strong> / Intera<strong>to</strong>m):<br />
DLOFC: Cumulative relative release fraction of core inven<strong>to</strong>ry after 200 h<br />
• Iodine-131: Fac<strong>to</strong>r of 2 higher<br />
• Cesium-137: Fac<strong>to</strong>r of 3 (design) <strong>to</strong> 6 (expected) lower<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
21<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Influence of Core Pass Number on Fuel Temp.<br />
mperature DLOFC [°C]<br />
Max. fuel te<br />
1650<br />
1600<br />
1550<br />
1500<br />
1450<br />
1400<br />
VSOP, nominelle NZL<br />
ZIRKUS, nominelle NZL<br />
VSOP, +10% NZL<br />
ZIRKUS, +10 % NZL<br />
VSOP, +10 % NZL, -10 % WL, -10 % WK<br />
1350<br />
5 6 7 8 9 10 11 12 13 14 15<br />
Core pass number<br />
Source of ZIRKUS data : Bernnat W., Feltes W., Model for reac<strong>to</strong>r physics calculation for <strong>HTR</strong> pebble bed modular reac<strong>to</strong>rs, Nuclear Engineering <strong>and</strong> Design 222 (2003)<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
22<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Influence of Core Pass Number on Cs-137 Release<br />
lease rate [m mol/s]<br />
Cs-137 rel<br />
6.0E-10<br />
5.0E-10<br />
4.0E-10<br />
3.0E-10<br />
2.0E-10<br />
1.0E-10<br />
55 Durchläufe core passes<br />
66 Durchläufe core passes<br />
77 Durchläufe core passes<br />
10 10 Durchläufe core passes<br />
15 15 Durchläufe<br />
core passes<br />
Kurve Curve maximaler of max. releases Freisetzungsraten<br />
0.0E+00<br />
0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200<br />
Accident time [h]<br />
Calculation with <strong>STACY</strong><br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
23<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Overview<br />
• Overview of Fission Product <strong>Code</strong>s at FZJ<br />
• Introduction <strong>to</strong> <strong>STACY</strong><br />
• Exemplary results for <strong>HTR</strong>-<strong>Module</strong><br />
• Exemplary results for <strong>HTTR</strong><br />
• Summary <strong>and</strong> outlook<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
24<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Fission product release calculation of <strong>HTTR</strong><br />
• Improvements in fission product release code:<br />
• Fickean diffusion within (hollow) cylindrical bodies<br />
• Usage of Monte-Carlo method <strong>to</strong> r<strong>and</strong>omize particle failure<br />
• Usage of burnup calculation <strong>to</strong> determine nuclide inven<strong>to</strong>ries instead of<br />
using simplified analytical equation<br />
→ Spatial resolved fission product release rates<br />
(so far, only block‐wise)<br />
• Burnup calculation with SERPENT<br />
• Monte-Carlo neutronics code incl. burnup calculation<br />
• Developed at VTT Technical Research Centre<br />
• Applied <strong>to</strong> <strong>HTTR</strong>, <strong>HTR</strong>-10, Konvoi (1300 MW class)<br />
etc. at FZJ<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
25<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Serpent Model of <strong>HTTR</strong><br />
Layer 2: 1: 4: 5: 6: 7: 3: 9: 8: Top Fuel Bot<strong>to</strong>m reflec<strong>to</strong>r<br />
layer<br />
reflec<strong>to</strong>r<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
26<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Cesium-137 release rates after 660 days<br />
Example:Layer 2 (blocks containing fuel only)<br />
-150<br />
-100<br />
5.64044E-11<br />
5.61247E-11<br />
5.61489E-11<br />
[mol/s]<br />
5.69754E-11<br />
5.56938E-11<br />
-50<br />
5.60440E-11<br />
6.64296E-11<br />
6.63254E-11<br />
5.51433E-11<br />
6.99919E-11<br />
Positio on 2<br />
0<br />
5.61235E-11 7.00011E-11 6.98107E-11 5.60894E-11<br />
6.64607E-1164607E 6.57313E-11<br />
11<br />
5.61670E-11 7.05264E-11 6.98409E-11 5.52424E-11<br />
6.98319E-11<br />
50<br />
5.55644E-11<br />
6.58100E-11<br />
6.55939E-11<br />
5.58302E-11<br />
5.55661E-11<br />
5.61413E-11<br />
5.58089E-11 5.58945E-11<br />
100<br />
5.55622E-11<br />
• Temperature input by JAEA<br />
• Fission product 150<br />
-150 calculation -100 -50 of one 0 representative 50 100 compact 150 per fuel block<br />
Position 1<br />
during “st<strong>and</strong>ard operation plan” of 660 days<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
27<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Cesium-137 release rates under NOC<br />
Relative Cesium-13 37-release fraction<br />
1.0E-01<br />
1.0E-02<br />
1.0E-03<br />
1.0E-04<br />
1.0E-05<br />
1.0E-06<br />
HT‐Phase<br />
FRESCO-II, Layer1<br />
FRESCO-II, Layer2<br />
FRESCO-II, Layer3<br />
FRESCO-II, Layer5<br />
<strong>STACY</strong>, Layer 1<br />
<strong>STACY</strong>, Layer 2<br />
<strong>STACY</strong>, Layer 3<br />
<strong>STACY</strong>, Layer 5<br />
0 110 220 330 440 550 660<br />
Time [d]<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
28<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Overview<br />
• Overview of Fission Product <strong>Code</strong>s at FZJ<br />
• Introduction <strong>to</strong> <strong>STACY</strong><br />
• Exemplary results for <strong>HTR</strong>-<strong>Module</strong><br />
• Summary <strong>and</strong> outlook<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
29<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Summary<br />
• Original codes have been modernized <strong>and</strong> merged <strong>to</strong> form one<br />
consistent code module <strong>STACY</strong><br />
• <strong>STACY</strong> has been extended <strong>and</strong> coupled with <strong>the</strong> code system<br />
VSOP, MGT-3D <strong>and</strong> <strong>the</strong> burnup code TNT <strong>to</strong> enable detailed<br />
spatially resolved fission product release calculations<br />
• Fission product release rate of short-living respectively long-<br />
living i nuclides are higher h respectively lower in comparison <strong>to</strong><br />
former calculation methods<br />
• <strong>STACY</strong> has been coupled <strong>to</strong> <strong>the</strong> backbone of <strong>the</strong> <strong>HTR</strong> <strong>Code</strong><br />
Package (currently being tested)<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
30<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Outlook<br />
• Fission product release of Cs-137, Sr-90, I-131, Ag-110m of<br />
<strong>HTR</strong>-10 (ARCHER Project)<br />
• VSOP model simulating running-in-phase is based on <strong>HTR</strong>-10<br />
model being developed as a contribution <strong>to</strong> CRP 5<br />
(prediction of first criticality)<br />
• Calibration of control rods (2D VSOP model)<br />
• Modeling of fluid mechanics in VSOP (THERMIX)<br />
• Development of irregular fuel shuffling scheme<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
31<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Thermal power during running-in phase <strong>HTR</strong>-10<br />
10<br />
9<br />
8<br />
Measured<br />
7<br />
Pow wer [MW]<br />
6<br />
5<br />
4<br />
3<br />
Condensed<br />
power<br />
his<strong>to</strong>ry<br />
2<br />
1<br />
0<br />
0 500 1000 1500<br />
Operation days<br />
Source: Fu LI, The <strong>HTR</strong>-10, operation performance <strong>and</strong> data collected, IAEA Consultancy Meeting, Vienna, 5-7 December 2011<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
32<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Calculated reactivity values by using VSOP<br />
• Calculated reactivity values during operation <strong>and</strong> zero power phase<br />
• Fine-tuning of <strong>the</strong> reactivity k eff = 1.0 would be easily possible with <strong>the</strong><br />
control rods margins<br />
operation<br />
zero power<br />
phase<br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
33<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013
Comparison of FRESCO-I <strong>and</strong> <strong>STACY</strong><br />
A. Xhonneux Technical Meeting on Re-evaluation of Maximum Operating Temperatures <strong>and</strong> Accident Conditions for<br />
34<br />
<strong>HTR</strong> Fuel <strong>and</strong> Structural Materials, Vienna,10-12 June 2013