ZIRAT

ZIRCONIUM ALLOY TECHNOLOGY PROGRAMME

The annual ZIRAT Programme brings together nuclear utilities, laboratories and fuel vendors worldwide to access one of the industry’s most comprehensive sources of zirconium alloy technology insight and fuel performance knowledge. Since 1996, ZIRAT has supported organisations in improving the reliability, safety, and economics of nuclear operations through expert evaluation of zirconium alloy materials and operational experience.

Each year, ZIRAT delivers an in-depth review and expert interpretation of the latest publicly available developments in zirconium alloy technology, highlighting key trends, risks, opportunities, and implications for fuel performance and future reactor operation.

Designed for decision-makers and technical specialists, ZIRAT provides actionable insight—not just data—helping members make informed strategic and operational decisions with confidence.

IZNA

INFORMATION ON ZIRCONIUM ALLOY TECHNOLOGY PROGRAMME

The annual IZNA Program is open to fuel vendors, regulators and research organisations. The IZNA deliverables are similar to those of the ZIRAT Program, however no annual Seminar is provided. A tailored seminar on site is provided at an additional fee. IZNA customers are fuel vendors, research laboratories and regulatory agencies world wide.The overall objective of the IZNA Program is to enable members to:

  • Identify potential zirconium alloy material problems and solutions related to nuclear fuel.

  • Gain increased understanding of material behaviour related to successful core operation.

The IZNA Program annually reviews the latest information on zirconium alloy technology. The review is the only complete, annually updated references on non-proprietary zirconium alloy technology in the industry. The information is organised by well established topics such as alloy research, corrosion, mechanical properties, dimensional stability, potential high burnup limitations etc.

LCC

LWR CHEMISTRY AND COMPONENT INTEGRITY PROGRAMME

The annual LCC Programme is focused on reactor coolant chemistry, secondary side chemistry, and Reactor Coolant System (RCS) material issues. The programme is open to nuclear utilities, manufacturers, vendors, research and engineering organisations, as well as regulatory authorities. Since its launch in 2004, the LCC Programme has become a well-established international forum for technical exchange and expert evaluation.

The overall objectives of the LCC Programme are to enable members to:

  • Improve understanding of reactor water chemistry and its impact on safe, reliable, and efficient plant operation, while maintaining the long-term integrity of Reactor Coolant System (RCS) materials and minimising radiation exposure.

  • Support plant operators in applying effective PWR secondary side chemistry practices to achieve safe, economical, and environmentally responsible operation with high plant availability, while reducing the risk of steam generator degradation, fouling, and carbon steel Flow Accelerated Corrosion (FAC).

  • Provide an independent international platform where experts can openly exchange experience, discuss operational challenges, and evaluate emerging chemistry and materials issues.