Product

ANSWERS

Data-driven solutions for nuclear safety, performance and operational efficiencies

Red haired woman in a white lab coat at a computer

Our ANSWERS® Software Service provides software and consultancy services for customers world-wide in the areas of reactor physics, radiation shielding, dosimetry, nuclear criticality, well logging and nuclear data.

Established software packages, dedicated helpline and support services, and the availability of experienced consultants and analysts provide a comprehensive capability to solve client issues in areas such as nuclear safety, plant performance and operational efficiency.

Explore our ANSWERS software service
  • Nuclear Criticality Safety -MONK

    MONK provides advanced geometry modelling and detailed continuous energy collision treatment to create realistic 3D models for an accurate Monte Carlo simulation of neutronic behavior.

  • Radiation Shielding and Dosimetry - MCBEND and RANKERN

    MCBEND calculates neutron, gamma-ray and charged particle transport in sub-critical systems using Monte Carlo radiation transport algorithms, as well as the coupling between these different radiation types.

  • Reactor Physics - WIMS and PANTHER

    WIMS can model a wide range of reactor physics problems ranging from simple pin cell reactivity calculations to whole core estimates of power flux distributions for all thermal reactor types, including research reactors.

  • PANTHER

    The leading neutron diffusion and thermal hydraulics code for the analysis of any thermal reactor core.

  • Nuclide Inventory - FISPIN

    FISPIN calculates the changes occurring in the numbers of atoms of the nuclides of various species (heavy isotopes or actinides, fission products and structural or activation materials) as a sample of nuclear fuel is subject to periods of irradiation and cooling.

  • Analysis of pressurized water reactors (PWRs)

    We’ve worked collaboratively with Tractebel Engineering and EDF Energy over many years to tackle issues and develop a new route for analyzing cores containing mixed oxide fuel (MOX) fuel and, to validate new WIMS/PANTHER methods for modelling PWRs containing a mixture of urate oxidase (UOX) and MOX fuels.