Nuclear Simulation Software

Software Products

Featured products

Studsvik Scandpower is the global leader in the development and support of fuel vendor-independent reactor analysis software.

We offer a full suite of licensing-grade software and engineering services to support operating utilities, fuel vendors, safety authorities, next-generation reactor developers, and research organizations. Our products are used throughout the world for reactor fuel and core design, analysis, and operational support.

Operation Support

Studsvik Scandpower’s integrated product line allows a single cycle-specific core model to simplify many aspects of plant operations from on-line core monitoring to real-time training simulation.

S3R

S3R enables cycle-specific core modeling on the training simulator

GARDEL

GARDEL is a fuel supplier independent advanced live core monitoring application with built-in reactivity management tools.

S3R

S3R enables cycle-specific core modeling on the training simulator in an easy-to-use, easy-to-update manner. S3R meets all industry and regulatory requirements for cycle-specific training applications.
S3R Flysheet

Superior Operator Training

S3R uses the same high-precision methods as the Studsvik core modeling and transient analysis software, increasing fidelity to the plant response and decreasing the risk of unphysical results.Because S3R models each fuel assembly and all instrumentation explicitly in three dimensions, operators can train on a model that exactly matches the plant conditions. It is now possible for an operator to go through reactivity manipulations on the simulator, instead of the plant, during initial licensing training.

Performance

One major performance hurdle in typical simulator core models is cross-section interpolation. S3R prebuilds its cross-section library, keeping only the data it actually needs for the current core life, resulting in a fast interpolation scheme.

S3R executes with a time-step and fixed iteration count to provide a stable and repeatable convergence, usually in under 250ms.

GARDEL

GARDEL is a fuel supplier independent advanced live core monitoring application with built-in reactivity management tools. Combining Studsvik’s state-of-the-art reactor analysis methods with efficient database technology and a customizable graphical user interface, GARDEL can help reduce uncertainties and conservatism that limit reactor operating efficiency.
GARDEL Flysheet

Automated Calculations

  • Reduce work required for engineering tasks
  • Reduce human performance errors
  • Define common procedures across the plant
  • Enable complex operations for modern operational requirements such as load follow

Benefits of Advanced Core Monitoring

  • Reduced training effort for nuclear engineers
  • Enables ATF modeling and monitoring
  • Intuitive and functional GUI
  • Reduce switching cost for fuel vendors
  • Highly flexible, always available
  • Fuel vendor independence
  • Common LWR platform provides resource flexibility and efficiency
  • Save time resolving unexpected operation needs or issues
  • Increase speed of communication between operations, reactor engineering, and core design

Reactor design, performance, and optimization

Studsvik Scandpower sets the industry standard for in-core fuel performance software with unparalleled accuracy, production-level run times, and easy-to-use input.

CASMO-5

CASMO5 is a state-of-the-art lattice physics code for modeling PWR and BWR fuel.

HELIOS-2

HELIOS-2 is a two-dimensional, generalized-geometry lattice physics transport code.

SIMULATE5

SIMULATE5 is a 3D, steady state, multi-group, nodal code for the analysis of both PWRs and BWRs

S5K

SIMULATE-5K is an advanced, two-group nodal code for transient analysis of both PWRs and BWRs

CMSBuilder

CMSBuilder is a graphical fuel management and loading pattern design suite

Peacock

Peacock is Studsvik’s new generalized-geometry, continuous energy

CASMO-5

CASMO5 is a state-of-the-art lattice physics code for modeling PWR and BWR fuel. Optimized to model challenging heterogeneous fuel designs, such as high mixed-oxide (MOX) concentrations and high burnable poison concentrations, CASMO5 is built to perform today and years into the future.
CASMO-5 Flysheet

Methodology

CASMO5 represents the culmination of Studsvik’s 30 years of experience in transport-based lattice physics. The 2D transport solution is based on the well-established Method of Characteristics with a linear source approximation, delivering unparalleled fidelity with production-level run times, even with today’s longer fuel cycles.

Improving Modeling Data

Exploiting the power of today’s computational hardware, CASMO5 requires fewer approximations and performs more rigorous solutions than previous generations of lattice physics codes.

Several significant physics enhancements, including resonance upscattering, higher-order Pn scattering, extended depletion chains, and a localized energy released-per fission model, make CASMO5 the most accurate lattice physics code available.

HELIOS-2

HELIOS-2 is a two-dimensional, generalized-geometry lattice physics transport code. By including the latest nuclear data and substantially expanded modeling capability, HELIOS-2 reaches far beyond the capabilities of previously available versions.
HELIOS-2 Flysheet

Methodology

HELIOS-2 transport calculations may be performed with either a collision probabilities or Method of Characteristics solver. Resonance self-shielding is calculated via the subgroup method, with a transport-based Dancoff calculation

Improved Modeling Detail

Exploiting the power of today’s computational hardware, HELIOS-2 requires fewer approximations and performs more rigorous solutions than the previous generation of lattice physics codes.

The addition of a Method of Characteristics solver allows larger models, such as multiple fuel bundles and fractional cores, to be calculated with fewer required computing resources.

SIMULATE5

SIMULATE5 is a 3D, steady state, multi-group, nodal code for the analysis of both PWRs and BWRs. SIMULATE5 delivers vendor independence and unparalleled accuracy for advanced core designers with increased heterogeneity and aggressive operating strategies.
SIMULATE5 Flysheet

Proven Results

Studsvik’s 30 years of experience producing flexible, highly accurate software solutions for the nuclear power industry is reflected in the state-of-the-art reactor physics methods and engineering features in SIMULATE5.

Fully capable of modeling all current and next generation PWRs, BWRs and SMRs with first-principle neutronic and thermal hydraulic calculations, SIMULATE5 provides a robust, single solution to core design and core analysis requirements.

Truly Advanced

Highly heterogeneous cores and aggressive operating strategies have pushed existing reactor analysis method to their limit.

Studsvik, the global leader in reactor analysis software, has developed SIMULATE5 to address these deficiencies and meet the demands of current and future core designs with cutting-edge neutronic and thermal-hydraulic methods not found in any other analysis package.

S5K

SIMULATE-5K is an advanced, two-group nodal code for transient analysis of both PWRs and BWRs. SIMULATE-5K delivers neutronic and thermal-hydraulic analysis with licensing-grade accuracy over a wide range of dynamic applications.
S5K Flysheet

Methodology

S5K leverages the power of SIMULATE5, the industry standard in nodal reactor analysis. Including cutting-edge neutronic methods and advanced engineering features, S5K delivers unparalleled fidelity with production-level run times.

S5K solves the transient three-dimensional, multi-group neutron diffusion equations, including models for delayed neutron precursors. Intranodal flux and power distributions within each node are used to compute the power, fuel temperatures, and enthalpies for every axial level of every fuel pin in the core during transients.

Each fuel assembly in the core is explicitly represented in the core thermal-hydraulics. For BWR operational transients, vessel and steam line models are capable of simulating acoustic effects in the steam line due to sudden valve closures or openings.

Proven Results

SIMULATE-5K (S5K) is built on the solid foundation of SIMULATE5, the industry-leading steady-state nodal reactor analysis code.

By explicitly modeling the detailed assembly-by-assembly neutronic and thermal-hydraulic behavior of the reactor core, S5K can be used to analyze a variety of core transients.

S5K has been successfully used by clients for stability analysis, reactivity insertion analysis, dynamic rod worth calculations, and past operational events.

CMSBuilder

CMSBuilder is a graphical fuel management and loading pattern design suite that provides core design engineers with a sophisticated interface to simplify assembly design, fuel shuffling and loading pattern evaluation.
CMSBuilder Flysheet

Maximize Core Design Efficiency

In today’s environment of constrained engineering resources, efficient navigation from scoping calculations to a final core design loading pattern is crucial.

Whether an organization is confirming a fuel vendor’s proposed design or designing the core themselves, it is essential to answer the hard questions:
-Does the fuel and core design proposed really meet the energy generation and thermal margin requirements?
– Could the loading pattern be improved? How can this be done efficiently and accurately?

CMSBuilder meets these challenges with an intuitive graphical interface seamlessly coupled to Studsvik’s industry-leading core analysis neutronic system (CMS5).

Improved Core Designs

Studsvik’s CMS5 code system has been applied in core design studies for virtually every PWR fuel and core design in existence today. Whether the fuel is high- or low- enriched, uranium or MOX, or contains industry standard discrete or integrated burnable poisons, when coupled with the CMS5 system, CMSBuilder can be used to improve the core design process.

CMSBuilder allows engineers to explore deeper into the core design space than would otherwise be possible due to its high degree of automation and visualization.

By allowing users to focus on using their design expertise instead of input creation and output extraction, CMSBuilder unlocks the power of the CMS5 system for engineers. Hand accounting and self-maintained spreadsheets will become a thing of
the past, improving users’ confidence in the accuracy and fidelity of their design patterns while increasing the pace of design iterations in today’s challenging environment.

Peacock

Peacock is Studsvik’s new generalized-geometry, continuous energy Monte Carlo code to support current and future reactor physics, shielding, and criticality analysis needs in industry.
Peacock Flysheet

Methodology

The Monte Carlo method is a powerful class of numerical techniques that rely on stochastic sampling of statistical distributions to simulate the behavior of physical systems. The Monte Carlo simulation of neutrons enables accurate predictions of criticality, the spatial fission rate distribution, generation
of homogenized multi-group cross section data, and other tallied quantities for nuclear reactor applications.
Flexible three-dimensional generalized geometry, continuous energy representation of cross section data, built-in depletion capability, and ease of use position Peacock as the next production-level, state-of-the-art analysis tool being developed by Studsvik.

Built-in Depletion Capability

Fuel depletion and isotope transmutation are of primary importance in the analysis of nuclear systems. Changes in the nuclide composition due to burnup can easily be modeled with Peacock. Using the advanced methods developed for CASMO5 and HELIOS2, Peacock includes the capability for highly accurate depletion calculations.

Spent Fuel Analysis and Storage Optimization

Managing spent nuclear fuel demands an increasing amount of engineering resources. We offer advanced, integrated solutions to analyze fuel pools/racks and optimize the loading of fuel storage casks.

MARLA

MARLA is an easy-to-use, highly automated tool for helping operations staff plan a fuel shuffle, manage the spent fuel pool, and load dry casks

SNF

Calculates isotopic concentrations, radiation source terms, and decay heat of spent light water reactor (LWR) fuel

MARLA

MARLA is an easy-to-use, highly automated tool for helping operations staff plan a fuel shuffle, manage the spent fuel pool, and load dry casks. MARLA addresses the industry needs related to fuel movement activities by fully integrating state-of-the-art analytical solutions to support plant operations.
MARLA Flysheet

Shuffle Planning

MARLA uses a Greedy algorithm coupled with Taboo search to design an in-core fuel shuffle that minimizes bridge motion while maximizing safety margin and reducing calculation time. MARLA performs in a few minutes what is otherwise an overnight calculation. MARLA also provides automation to design a full core off-load in lieu of an in-core shuffle. Automated licensing-grade shutdown margin calculation at each step. No working knowledge of SIMULATE required.

Point. Click. Done.

MARLA uses point-and-click graphics for quick and easy definition of all maintenance work scheduled to take place during the refueling outage. Drag- and-drop functionality allows user to easily make modifications to any automated sequence and accelerates the training of new personnel.

Built on a solid foundation of Java, MARLA supports multiple screens, docking and undocking of various windows showing the core, the pool, and casks.

SNF

SNF calculates isotopic concentrations, radiation source terms, and decay heat of spent light water reactor (LWR) fuel. By using the detailed, 3D power history from SIMULATE and isotopic inventories from CASMO, SNF provides the most accurate spent fuel analysis available.
SNF Flysheet

Created at the Request of Customers:

  • Explicitly calculate decay heat.
  • Explicitly calculate decay chains for safeguards isotopic inventory reporting.
  • Rapidly determine source term in pools, casks, and final repository.

Remove Complication. Remove Cost.

Replace the process of running ~800+ code runs with five lines of input to SNF, which eliminates large consulting fees and long project times.
Best-Estimate Source Term reduces typical uncertainties.
State-of-the-Art, most recent Nuclear Data (ENDF/ B-VIII.0 available) removes the need for hand- calculated corrections from older libraries.

Extensive Validation

SNF has been validated against both international measurements and existing reference codes, such as ORIGEN.
Source term validation has been performed against measured neutron emission rates of isotopes such as 242Cm, 244Cm, and 246Cm.
SNF also excelled in comparisons with fuel assembly decay heat measurements of a large number of BWR and PWR spent fuel assemblies at the CLAB storage facility in Sweden.

For further information, please contact us.

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