Recent Developments of the

Transcription

1 emeinschaft der Helmholtz-Ge Mitglied d Recent Developments of the HTR Code Package (HCP) Forschungszentrum Jülich, Germany Technical Meeting on Re-evaluation of Maximum Operating Temperatures g p g p and Accident Conditions for HTR Fuel and Structural Materials IAEA Headquarters,Vienna, June

2 Motivation for HCP Developement Overcome current drawbacks and limitations of individual legacy codes Conservation of knowledge in a contemporary way for future demands Speed up implementation times for necessary (future) model extensions Reduce software maintance costs by avoiding code duplication Increase the numerical stability by applying recent Fortran coding standards and new implementations in C++ to use objects and templates Design, implementation ti and validation of software for the simulation of an HTR reactor core applying the latest programming techniques and standards 2

3 Overview of the HCP 3

4 Input Concept 4

5 Input Concept - Data Library One consistent data library for all HCP modules: cross sections, scattering matrices, decay data, FP release data,... One master file DataLibrary.xml (ENDF/B-VII.0, JEFF 3.1.1,...) Each nuclide has its own data file linked to the master (e.g. Th-232.xml) endfb70.xml Th-232.xml U-235.xml Pu-239.xml 5

6 Input Concept - Data Library A new code HCPLibGen is being developed to build the data library for the HCP Nuclide objects are filled by the code step by step with different kind of data sets Basic interface in HCPLibGen therefore is the HcpNuclide object, this is the same object (same piece of code) used in HCP later on basic data decay data cross section data Fission yield data other data Program flow 6

7 Input Concept - Model and Scenario Model: Definition of the reactor model Mesh grid Material assignment Flow curves (in case of fuel shuffling of pebble bed) Basic data for decay data for cross sections for fission yields for other data 3842 nuclides 3842 nuclides 393 nuclides 31 nuclides Scenario: Definition of the program calculations and boundary conditions program flow Definition of the program flow Module specific (MGT-N/-T, TNT, SHUFLE, STACY, STAR) Program specific (e.g. output) 7

8 Physics Modules 8

9 Physics Modules - Overview Physics Model Former Code HCP Module 3D Neutronics 3D Fluid Dynamics MGT-3D Graphite Corrosion by Air and Water MGT-T MGT-N Depletion and Energy Release VSOP, Origen-Juel NAKURE TNT Fuel Management VSOP SHUFLE FP Release / Fuel Performance Graphite Dust Deposition and Resuspension FRESCO I/II PANAMA STACY --- STAR 9

10 Physics Modules - MGT-N and MGT-T Multi Group TINTE (Time dependent Neutronics and Temperatures) Main Features: Basic data for 3842 nuclides Time dependent neutronics and fluid dynamics for 3D reactor models Feedback between neutronics and fluid dynamics I/Xe dynamics decay data for cross sections for fission yields for other data 3842 nuclides 393 nuclides 31 nuclides Basic graphite corrosion chemistry Local and non-local nuclear heat sources Decay heat calculations according to DIN standard (German standard) program flow Spectrum calculation code with (so far) up to 43 energy groups Gas flow and mixing Heat transport 10

11 MGT-T - Simulation Example: Unit Cell Temperature distribution in representative unit cell of prismatic block Coolant bore hole Fuel 11

12 MGT-T - Simulation Example: Unit Cell Comparison with CFX calculation Maximum temperature difference : 10 C CFX MGT-3D (Unit-cell) 1150 Tem mperature [ C C] Distance to fuel rod center [cm] 12

13 Benchmark of Prismatic Block Calculation FZJ participates in OECD/NEA LOFC Project Accident tests are being / will be performed in HTTR: 1. LOFC at part load, 9 MW (post calculation) 2. LOFC at full load, 30 MW (predictive calculation) MGT-3D will be used to calculate temperature distribution and eventually the time point of recriticality Monte-Carlo neutronics Code SERPENT is being used to simulate the state t of fhttr at tthe beginning i of fthe LOFC as a boundary condition for MGT-3D Newly developed interface code generates mesh data out of block/ pin-wise data 13

14 Physics Modules - TNT TNT : Topological Nuclide Transmutation Main Features: Calculation of time-dependent nuclide amounts due to decay or particle-induced reactions by using the graph theory and a topological solver Calculation of thermal power separately by fission, decay and Basic data capture for decay processes data for cross sections for fission yields for other data 3842 nuclides 3842 nuclides 393 nuclides 31 nuclides Usage of energy-dependent fission yields Determination of burnup measures like FIMA or MWd/kgHM Application of graph theory to model complex nuclide chains program flow Optimized for performance ( minimum graph approach ) Can be runned parallel for different batches with OpenMP 14

15 TNT - Verification of Decay Heat Calculation LWR, 1300 MW class 200 th] Decay po ower [MW Way-Wigner Glasstone 2nd TNT 0 1E+01 1E+02 1E+03 1E+04 1E+05 1E+06 1E+07 Time [s] 15

16 TNT - New Visualisation Features Colored edges for different reactions Different edge types for decay (solid) and neutron induced reactions (dashed) d) Stable nuclides have thicker vertex Edges with different rates have different thickness ( scaled logarithmically) Visualisation of short- and long-lived nuclides Grap ph for data a set C

17 Physics Modules - SHUFLE Software for Handling Universal FueL Elements Main Features: Shuffling of both pebbles and blocks simulation of conical piles Basic data for 3842 nuclides mesh-specific filling factors (e.g. simulation of seismic effects) decay data for cross sections for fission yields for 3842 nuclides 393 nuclides 31 nuclides azimuthally differing flow velocities (3D fuel shuffling) Measured flow paths [1] fuel shuffling includes external facilities (e.g. fuel storages, fuel production plant, ) same mesh grid for pebble flow and other code modules Silo drainage [2] [1] Yang, X.: Experimental Investigation on Feasibility of Two-Region-Designed Pebble-Bed High-Temperature Gas-Cooled Reactor, INET, 2008 [2] Kamrin K., Rycrof C., Bazant M., The stochastic flow rule: a multi-scale model for granular plasticity, MIT. Cambridge,

18 SHUFLE - Graph Theory Graph connecting fuel collections Graph connecting meshes in fuel collection Core 18

19 SHUFLE First Validation Step 100 [%] of tagged pebbles ANABEK SHUFLE ANABEK facility Discharged fraction Recycled fraction of core volume (RCV) [%] 19

20 Output Concept 20

21 Output Concept 21

22 Output Concept - Examples Message example: ***************************************************************** 11 :04:12 INFO TNT TNT calcburnupmeasures ***************************************************************** number of fissions: e 20 average power W : FIMA % : MWd /kg HM : Data field example: time y ; H 001 ; He 004 ; V 053 ; e 00; e 00; e 00; e 00; e 00; e 07; 5,4062e 08; e 22;... 22

23 HCP Backbone (Main Program) 23

24 Summary Existing programs have been refactored, new modules were developed As a next step they will be coupled to the HCP backbone Basic data for 3842 nuclides decay data for cross sections for fission yields for other data 3842 nuclides 393 nuclides 31 nuclides A first prototype will be finished in 2014 (beta testers are welcome) Modules can also be used as stand alone codes and be applied to different physics problems (reactors, radionuclide production, waste repositories) program flow 24

25 Memory Requirements for Datamodel 25