Testing Framework for Nuclear Fuel Handling Machines: Design Requirements, Standardization, Specific Technical Issues, and Engineering Challenges

In the context of Romania's expanding nuclear energy program and global initiatives focused on Generation IV advanced reactors, the testing of nuclear fuel handling machines has become essential for ensuring safe and efficient reactor operation. This paper analyzes the applicable design requirements, international standards (IAEA SSG-63, REGDOC-2.4.5), and testing procedures for fuel handling equipment, with emphasis on validated technical solutions used in CANDU, PWR, BWR, SFR, and LFR reactors. The specific characteristics of CANDU systems - enabling online refueling under high-pressure and high-temperature conditions - are highlighted, along with the advantages of Out-of-Pile testing using dedicated facilities. Romania's extensive experience gained through the complete testing of Fuel Handling Machines (F/M) for Unit 2 at CNE Cernavodă provides a strong foundation. This expertise will inform the upcoming test campaigns for Units 3 and 4, to be conducted at the F/M Testing Rig developed at ICN Pitești, which also includes a custom fullscope simulator. The paper discusses specific testing challenges, from replicating thermal-hydraulic conditions to addressing the absence of radiological effects, and outlines the key lessons learned for future generations of equipment. Finally, emerging research directions are explored, including AI integration, advanced automation, and digitally assisted testing. These developments aim to enhance equipment reliability, reduce maintenance time, and enable realistic validation of fuel handling technologies tailored for the next generation of nuclear systems.