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.

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.

PEACOCK

Peacock is the advanced Monte Carlo analysis code for the present and future nuclear reactor community.

Accuracy

By leveraging decades of Studsvik experience in processing evaluated nuclear data, pre-generated neutron data libraries are delivered which are ready to
be used by the analyst. Peacock eliminates the data preparation requirements common to other Monte Carlo codes. Those users who have generated problem-specific temperature libraries for other MC codes will be happy to know that Peacock will support automatic temperature interpolation using the pre-built libraries. Industry standard nuclear data evaluations such as ENDF/B-VII.1, as well as cutting-edge evaluations like ENDF/B-VIII.1, will be the foundation and starting point for the Peacock libraries.

Flexible Geometry

Flexible geometry modeling Constructive Solid Geometry (CSG) in Peacock allow the user to analyze fuel concepts beyond current designs. For instance, advanced concepts involving particles with encapsulated fuel, as shown in the figure, can be readily modeled using Peacock’s flexible geometry description.

Applications

Peacock is being developed for reactor physics applications in advanced reactors and conventional Light Water Reactors (LWRs). As shown in the figure in the
upper right, Peacock can be used as a lattice physics tool to model typical Pressurized Water Reactor (PWR) fuel assembly geometry and obtain homogenized data to support downstream full-core calculations.

Requirements

Learn more about our software requirements using the link below

Requirements

Nuclear Quality Assurance

Peacock will fully comply with the American Society of Mechanical Engineers (ASME) Nuclear Quality Assurance-1 (NQA-1) standard. Peacock stands apart from other Monte Carlo tools with respect to Quality Assurance (QA). Additionally, Peacock will be 10 CFR 50/Appendix B compliant with 10 CFR 21 reporting.

For further information, please contact us.