部門設立30周年記念出版:Vol.4沸騰水型原子炉

（BWR炉心燃料の研究開発）

抄録

In Chapter 3 of this book, the step-by-step research and development of BWR reactor core and fuel assembly are described to realize uranium savings by high burnup fuel and MOX fuel. This presentation described the reactor internal and coolant flow paths in a reactor pressure vessel, advances in fuel development, thermal-hydraulic design, proving test on thermal-hydraulic performance, new design criteria (Post-Boiling Transition standard), and the issue in developing the future fuel assembly.