Periodic Reporting for period 2 - McSAFE (High-Performance Monte Carlo Methods for SAFEty Demonstration- From Proof of Concept to realistic Safety Analysis and Industry-like Applications)
Okres sprawozdawczy: 2019-03-01 do 2020-08-31
This summary describes the main achievements of H2020 McSAFE project. The main achievements can be summarized as follows:
- First of the kind multi-physics Monte Carlo / thermal hydraulic coupled codes for the analysis of transients e.g. using Serpent2/SCF, Tripoli4/SCF.
- Novel and advanced multi-physics codes (e.g. Serpent2/SCF/TU) based on the ICoCo able to perform full core depletion calculation at pin level due to collision-based domain decomposition, improved memory management of TU, and optimized convergence.
- Two robust coupling methods:ICoCo and an internal master-sleeve at pin-level
- Massive use of HPC at KIT and in Europe paved the way for truly first-of-the-kind detailed simulations of full LWR-cores with square and hexagonal fuel assemblies at pin/subchannel level.
- The implementation of different variance reduction methods for both depletion and dynamic simulations to the reduction of the statistical noise and increasing the prediction accuracy
- McSAFE provided validated tools based on test data (SPERT-III E REA) and plant data PWR (square FA) and VVER-1000 Temelin (hexagonal FA)
- Innovations of Monte Carlos codes to facilitate the prediction of safety-relevant parameters with low statistical uncertainty and with few iterations, stable/robust schemes for depletion and criticality simulations e.g. proper variance reduction methods, optimal parallel execution, etc.
- McSAFE tools rerpresent a huge and significant step towards industry-like applications of the novel MC-based multiphysics tools for the safety assessments of LWR-cores.
- Inherent features of MC-codes to describe the geometrical details of cores have high potential for their application to other reactor designs e.g. of Generation III and research reactors
- Complementary expertise of the McSAFE-partners (universities: KIT, KTH), research centres (KIT, CEA, UJV, HZDR, VTT, JRC Karlsruhe), utilities (PEL, CEz and EdF), etc. were crucial for mastering the challenges.
- First of the kind multi-physics Monte Carlo / thermal hydraulic coupled codes for the analysis of transients e.g. using Serpent2/SCF, Tripoli4/SCF.
- Novel and advanced multi-physics codes (e.g. Serpent2/SCF/TU) based on the ICoCo able to perform full core depletion calculation at pin level due to collision-based domain decomposition, improved memory management of TU, and optimized convergence.
- Two robust coupling methods:ICoCo and an internal master-sleeve at pin-level
- Massive use of HPC at KIT and in Europe paved the way for truly first-of-the-kind detailed simulations of full LWR-cores with square and hexagonal fuel assemblies at pin/subchannel level.
- The implementation of different variance reduction methods for both depletion and dynamic simulations to the reduction of the statistical noise and increasing the prediction accuracy
- McSAFE provided validated tools based on test data (SPERT-III E REA) and plant data PWR (square FA) and VVER-1000 Temelin (hexagonal FA)
- Innovations of Monte Carlos codes to facilitate the prediction of safety-relevant parameters with low statistical uncertainty and with few iterations, stable/robust schemes for depletion and criticality simulations e.g. proper variance reduction methods, optimal parallel execution, etc.
- McSAFE tools rerpresent a huge and significant step towards industry-like applications of the novel MC-based multiphysics tools for the safety assessments of LWR-cores.
- Inherent features of MC-codes to describe the geometrical details of cores have high potential for their application to other reactor designs e.g. of Generation III and research reactors
- Complementary expertise of the McSAFE-partners (universities: KIT, KTH), research centres (KIT, CEA, UJV, HZDR, VTT, JRC Karlsruhe), utilities (PEL, CEz and EdF), etc. were crucial for mastering the challenges.
Main results of WP2:
- New depletion scheme for controlling the time steps of MC-burnup calculations
- Development and implementation of the collision based domain decomposition for Serpent
- Inprovement of the fission source convergence based on the response matrix importance solver to reduce the number of inactive cycles
- Optimization of the coupled MC /TH solvers to solve full real cores
- Demonstration of the new capabilities of the McSAFE-tools to perform depletion calculation considering N, TH and TM feebacks at pin level
Main results of WP3:
- Sucessful integration of Monte Carlo codes (SERPENT, TRIPOLI, MONK), and SCF and TRANSURANUS in SALOME
- Integration of Serpent/SCF into the SALOME platform
- Implementation of a modular and flexible coupling approach of MC, TH and TM codes based on the ICoCo-methodology
- Demonstration of the capability of the pre-processor of SCF generating very large models of full cores (square and hexagonal) for industry-like problems
Main Results of WP4:
- New coupled codes e.g. Serpent/SCF, Tripoli/SCF and MCNP/SCF developed for the analysis of transients
- Variance reduction methods for time-dependent MC-codes implemented for TRIPOLI to perform transient analysis with sufficient low statistical uncertainty
- A zero-variance schemes for time-dependent transport with SERPENT developed including contribution of precursors.
- The VR-technique "implicit branchless collision method" implemented in SERPENT.
- Implementation of efficient methods for parallel execution in massively parallel architecture.
- New capabilities demonstrated by solving a REA in a PWR minicore 3x3 FA.
Main results of WP5:
- The validation of the coupled code SERPENT/SCF/TU performed by using plant data of Pre-Konvoi and VVER 100 reactor.
- Comparison of critical boron, axial and radial power profiles predicted by the tools with the ones of the measurements show low deviations.
- Validation of dynamic MC-codes performed using SPERT III E REA. This are unique and first-of-the-kind results.
- McSAFE tools can solve industry-relevant problems such as a REA in a PWR UOX-MOX
Exploitation and dissemination:
- Creation of the McSAFE User Group for testing the McSAFE tools
- Successful training course with 28 participants
- Regular newsletters elaborated
- Three syntehsis reports written for public
Disseminaition of methods and tools done by means of:
- McSAFE public homepage
- Presentations national / international events, whorkshops (6),
- Conference papers (21), and
- Journal papers (17).
- New depletion scheme for controlling the time steps of MC-burnup calculations
- Development and implementation of the collision based domain decomposition for Serpent
- Inprovement of the fission source convergence based on the response matrix importance solver to reduce the number of inactive cycles
- Optimization of the coupled MC /TH solvers to solve full real cores
- Demonstration of the new capabilities of the McSAFE-tools to perform depletion calculation considering N, TH and TM feebacks at pin level
Main results of WP3:
- Sucessful integration of Monte Carlo codes (SERPENT, TRIPOLI, MONK), and SCF and TRANSURANUS in SALOME
- Integration of Serpent/SCF into the SALOME platform
- Implementation of a modular and flexible coupling approach of MC, TH and TM codes based on the ICoCo-methodology
- Demonstration of the capability of the pre-processor of SCF generating very large models of full cores (square and hexagonal) for industry-like problems
Main Results of WP4:
- New coupled codes e.g. Serpent/SCF, Tripoli/SCF and MCNP/SCF developed for the analysis of transients
- Variance reduction methods for time-dependent MC-codes implemented for TRIPOLI to perform transient analysis with sufficient low statistical uncertainty
- A zero-variance schemes for time-dependent transport with SERPENT developed including contribution of precursors.
- The VR-technique "implicit branchless collision method" implemented in SERPENT.
- Implementation of efficient methods for parallel execution in massively parallel architecture.
- New capabilities demonstrated by solving a REA in a PWR minicore 3x3 FA.
Main results of WP5:
- The validation of the coupled code SERPENT/SCF/TU performed by using plant data of Pre-Konvoi and VVER 100 reactor.
- Comparison of critical boron, axial and radial power profiles predicted by the tools with the ones of the measurements show low deviations.
- Validation of dynamic MC-codes performed using SPERT III E REA. This are unique and first-of-the-kind results.
- McSAFE tools can solve industry-relevant problems such as a REA in a PWR UOX-MOX
Exploitation and dissemination:
- Creation of the McSAFE User Group for testing the McSAFE tools
- Successful training course with 28 participants
- Regular newsletters elaborated
- Three syntehsis reports written for public
Disseminaition of methods and tools done by means of:
- McSAFE public homepage
- Presentations national / international events, whorkshops (6),
- Conference papers (21), and
- Journal papers (17).
The progress achieved in McSAFE considered as beyond state-of-the-art is listed below:
- Development of methods for stable depletion calculation, fission source acceleration and improved convergence behavior of MC/TH-solvers,
- Collision based domain decomposition for MC-codes to reduce the memory requirement of large depletion problems,
- Modular and flexible coupling methods based on ICoCo for neutronics, thermal-hydraulics and thermo-mechanics coupling using different geometries (square and hexagonal fuel assemblies),
- Optimized scalability of MC-codes when running in an HPC-environment
- Developed coupled codes facilitate the direct prediction of local safety parameters without approximations
- Dynamic capability of MC-codes coupled with subcahnnel codes paving the way for unique transient analysis and local safety parameters prediction
- First validation of transient capability of MC-based McSAFE tools using experimental data about a Rod Ejection Accident (SPERT III E REA)
The potential impacts of main outcomes of the McSAFE-projects can be summarized as follows:
• Impact on innovation capacity and integration of new knowledge within EU in the field of reactor safety:
- deliver novel numerical tools not available before for transient analysis;
- provide validated simulation tools which may serve as reference solutions to deterministic codes
- Pave the way for the use of MC-based multiphysics codes during the licensing process of different reactor designs
• Impact on interaction with civil society and stakeholders:
- MC-based McSAFE-tools can be used by nuclear community (regulators, utilities, manufacturers) to reduce conservatism and better predict safety margins.
• Impact on reinforcing the European leadership’s nuclear engineering by providing advanced methods to better assess the safety of NPP and make NPP operation more flexible while keeping high safety standards.
• Economic impact:
- EU-users will profit from the extended capabilities of the tools, which may lead to a decrease of conservatism of engineering factors and to better fuel exploitation and fuel cycle economy in general.
- European users of the McSAFE tools can take economical profit by using them to optimize and increase the performance of core designs
• Environmental impact:
- The McSAFE-tools contribute to better predict safety features of core designs and to reduce probability of accidents leading to a release of radioactivity, as well as to the EU goals pf low carbon economy.
• The societal impact of the project
- it is reflected by the fact that the risks of potential accidents is reduced by the use of novel McSAFE tools under development.
- Development of methods for stable depletion calculation, fission source acceleration and improved convergence behavior of MC/TH-solvers,
- Collision based domain decomposition for MC-codes to reduce the memory requirement of large depletion problems,
- Modular and flexible coupling methods based on ICoCo for neutronics, thermal-hydraulics and thermo-mechanics coupling using different geometries (square and hexagonal fuel assemblies),
- Optimized scalability of MC-codes when running in an HPC-environment
- Developed coupled codes facilitate the direct prediction of local safety parameters without approximations
- Dynamic capability of MC-codes coupled with subcahnnel codes paving the way for unique transient analysis and local safety parameters prediction
- First validation of transient capability of MC-based McSAFE tools using experimental data about a Rod Ejection Accident (SPERT III E REA)
The potential impacts of main outcomes of the McSAFE-projects can be summarized as follows:
• Impact on innovation capacity and integration of new knowledge within EU in the field of reactor safety:
- deliver novel numerical tools not available before for transient analysis;
- provide validated simulation tools which may serve as reference solutions to deterministic codes
- Pave the way for the use of MC-based multiphysics codes during the licensing process of different reactor designs
• Impact on interaction with civil society and stakeholders:
- MC-based McSAFE-tools can be used by nuclear community (regulators, utilities, manufacturers) to reduce conservatism and better predict safety margins.
• Impact on reinforcing the European leadership’s nuclear engineering by providing advanced methods to better assess the safety of NPP and make NPP operation more flexible while keeping high safety standards.
• Economic impact:
- EU-users will profit from the extended capabilities of the tools, which may lead to a decrease of conservatism of engineering factors and to better fuel exploitation and fuel cycle economy in general.
- European users of the McSAFE tools can take economical profit by using them to optimize and increase the performance of core designs
• Environmental impact:
- The McSAFE-tools contribute to better predict safety features of core designs and to reduce probability of accidents leading to a release of radioactivity, as well as to the EU goals pf low carbon economy.
• The societal impact of the project
- it is reflected by the fact that the risks of potential accidents is reduced by the use of novel McSAFE tools under development.