The radionuclide composition of, and emitted radiation in, spent nuclear fuel from the future MYRRHA facility have been studied using depletion simulations to understand potential consequences for safeguards verification using non-destructive assay. The simulations show that both the gamma-ray and neutron emission rates in spent MYRRHA assemblies are lower than in spent PWR UO₂ and MOX assemblies. In addition, gamma-ray emission rates from ¹³⁴Cs and ¹⁵⁴Eu are considerably lower, and the total neutron emission rate in MYRRHA fuel is much less sensitive to fuel burnup and cooling time. The main reason is that the fast neutron spectrum in MYRRHA affects the radionuclide production in the fuel. One result is that ²⁴⁴Cm, the main contributor to the neutron emission in spent light water reactor fuel, has a limited production in MYRRHA. Consequently, neutron-detection techniques could be used to more directly assay the plutonium content of spent MYRRHA fuel.

已经使用消耗模拟研究了来自未来 MYRRHA 设施的乏核燃料的放射性核素成分和发射的辐射，以了解使用非破坏性分析进行保障核查的潜在后果。模拟表明，废 MYRRHA 组件中的伽马射线和中子发射率均低于废 PWR UO ₂和 MOX 组件。此外，来自¹³⁴ Cs 和¹⁵⁴ Eu 的伽马射线发射率要低得多，而且 MYRRHA 燃料中的总中子发射率对燃料燃烧和冷却时间的敏感性要低得多。主要原因是 MYRRHA 中的快中子谱影响了燃料中放射性核素的产生。结果之一是²⁴⁴Cm 是乏轻水反应堆燃料中中子排放的主要贡献者，在 MYRRHA 中的产量有限。因此，中子检测技术可用于更直接地测定 MYRRHA 燃料中的钚含量。