Opening book details…
About this nonfiction
PWR plant container sizing criteria : studies of transient temperature and pressure in plant container following primary coolant system rupture by R M Rome; T R Moffette; Bettis Atomic Power Laboratory.; U.S. Atomic Energy Commission.; Westinghouse Electric Corporation is a nonfiction available to read on EtoBox.
It is typically read by self-directed learners exploring a subject in depth.
Common subject areas: history, science, philosophy, social sciences.
- Author
- R M Rome; T R Moffette; Bettis Atomic Power Laboratory.; U.S. Atomic Energy Commission.; Westinghouse Electric Corporation
- Publisher
- Office of Technical Services, Department of Commerce, 1957.
- Published
- 1957
- Language
- EN
- Category
- nonfiction
More by R M Rome; T R Moffette; Bettis Atomic Power Laboratory.; U.S. Atomic Energy Commission.; Westinghouse Electric Corporation
Similar books
- PWR Vapor Container Design Criteria. — U.S. Atomic Energy Commission (1954)
- Hydrogen Flammability Data and Application to PWR Loss-of-coolant Accident / Z.M. Shapiro, T.R. Moffette. — Z. M. Shapiro (1957)
- Transient Temperature in Infinite Plates, Infinite Cylinders, and Spheres Following a Simultaneous Step Change in Internal Heat Generation Rate, Coolant Temperature and Heat Transfer Coefficient — Lester G. Epel (1958)
- An Assessment of the Failure Rate for the Beltline Region of PWR Pressure Vessels During Normal Operation and Certain Transient Conditions / R.M. Gamble, J. Strosnider, Jr. — R. Gamble (1981)
- Pressure Vessel and Piping Codes Applicable to the PWR Reactor Plant / J.F. Dobinsky, M.B. Andrew, T.R. Moffette. — J. F. Dobinsky (1957)
- Transient Boiling Behavior of the Yankee Reactor Following Loss of Coolant Flow — J. P. Cunningham (1961)