Skip Nav Destination
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and StandardsAvailable to Purchase
Editor
ISBN:
9780791860199
No. of Pages:
802
Publisher:
ASME Press
Publication date:
2014
eBook Chapter
15 Generation III+ PWRs Available to Purchase
Page Count:
31
-
Published:2014
Citation
Schwab, EK, Parece, M, & Onozuka, M. "Generation III+ PWRs." Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards. Ed. Rao, K. ASME Press, 2014.
Download citation file:
From the commissioning of the first commercial nuclear reactor more than 50 years ago, the nuclear power industry has been developing and improving reactor technology with particular emphasis on reliability and safety. There are several generations of reactors that have been developed or are being developed. These reactors are generally categorized as Generation I, II, III, III+, and IV reactors. Figure 15.1 illustrates the technology distilled from 50 years of successful nuclear operating experience that has led to the Generation III+ pressurized water reactors (PWRs).
Topics:
Pressurized water reactors
15.1 Introduction
15.2 Scope of Commentary
15A AP1000® PWR
15B EPR
15C US-APWR
This content is only available via PDF.
You do not currently have access to this chapter.
Email alerts
Related Chapters
Temperature-Shift of Void Swelling Observed in Annealed Fe-18Cr-10Ni-Ti Stainless Steel Irradiated in the Reflector Region of BOR-60
Effects of Radiation on Materials: 19th International Symposium
Investigation of In-Pile Grown Corrosion Films on Zirconium-Based Alloys
Zirconium in the Nuclear Industry: Eleventh International Symposium
Development and Status of Embrittlement Trend Correlations in France
Radiation Embrittlement Trend Curves and Equations and Their Use for RPV Integrity Evaluations
Review of Pressurized-Water-Reactor-Related Thermal Shock Studies
Fracture Mechanics: Nineteenth Symposium
Related Articles
Integrated Power Recovery Using Markov Modeling
J. Eng. Gas Turbines Power (November,2011)
Experimental and Numerical Modeling of Transition Matrix From Momentum to Buoyancy-Driven Flow in a Pressurized Water Reactor
J. Eng. Gas Turbines Power (January,2009)