B.E. Boyack

Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology

B.E. Boyack, I. Catton, Romney B. Duffey et al. · Nuclear Engineering and Design · 1990 · 205 citations · Full text

Reliability, Safety Engineering, Safety-critical System +13

The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis

Gary E. Wilson, B.E. Boyack · Nuclear Engineering and Design · 1998 · 172 citations

Safety-critical System, Engineering, Pirt Process +13

An integrated structure and scaling methodology for severe accident technical issue resolution: Development of methodology

N. Zuber, Gary E. Wilson, Mamoru Ishii et al. · Nuclear Engineering and Design · 1998 · 123 citations

Engineering, Safety Management, Incident Management +13

Quantifying reactor safety margins: Application of code scaling, applicability, and uncertainty evaluation methodology to a large-break, loss-of-coolant accident

B.E. Boyack, Romney B. Duffey, G.E. Wilson et al. · 1989 · 100 citations

Reliability, Safety Engineering, Safety-critical System +14

Quantifying reactor safety margins part 3: Assessment and ranging of parameters

W. Wulff, B.E. Boyack, I. Catton et al. · Nuclear Engineering and Design · 1990 · 62 citations

Reliability, Safety Engineering, Engineering +10