Pressurised Water Reactors

1st Edition - May 1, 2024

Editors: Yurugi Kanzaki, Hidehito Mimaki, Tomofumi Yamamoto

Paperback ISBN:

9 7 8 - 0 - 1 2 - 8 2 3 5 8 3 - 6

eBook ISBN:

9 7 8 - 0 - 1 2 - 8 2 3 5 8 4 - 3

Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very… Read more

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Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very comprehensive reference, beginning with its history. The reader is then guided through optimum design processes for PWRs, considering safety throughout. The authors then discuss thermal-hydraulic aspects within the PWR system and inside the reactor core, making this a valuable resource for nuclear and thermal engineers and researchers. Combining their wealth of experience, the book presents in-depth knowledge on the advancement and improvement of fuel rods that is gleaned from decades of experience and lessons learned.The inclusion of analysis codes for the design and safety elements ensure makes this a unique reference which will provide the reader with a solid understanding which they can transfer to their own professional and research settings. Future prospects for next generation PWR and Small Modular Reactors are also discussed, giving the reader a basis for further research of their own.

1. History of PWR development

1.1 Early research and development of PWR

1.2 Technology importation and standardization
(1) The first standardization
(2) The second standardization

1.3 Improvement of system and construction
(1) Reduction of construction period
(2) Other improvements

1.4 Construction experience and operational performance

2. PWR plant designs

2.1 Features of PWR plant
(1) 2-loops, 3-loops, 4-loops
(2) APWR

2.2 PWR major systems
(1) Primary loop
(2) Reactor vessel and internals
(3) Pressurizer
(4) Reactor coolant pump
(5) Secondary loop
(6) Containment system
(7) Turbine and generator system

2.3 Auxiliary systems
(1) Boron recycle system (BRS)
(2) Boron thermal regeneration system (BTRS)
(3) Residual heat removal system (RHRS)
(4) Reactor coolant system
(5) Steam Generator Blowdown processing system
(6) Other systems and components

2.4 Safety systems
(1) Safety injection system(SIS) and components
(2) High-pressure injection
(3) Emergency feedwater for secondary loop (EFWS)
(4) Component cooling water system (CCWS)
(5) Containment isolation system (CIS)
(6) Containment Spray system (CSS)
(7) Hydrogen control
(8) Other systems and components

2.5 Major instrumentation and controls
(1) Plant start-up
(2) Power operation
(3) Plant shutdown

3. Nuclear thermal-hydraulics of reactor core and fuel assembly

3.1 Reactor core construction and flow paths in reactor pressure vessel

3.2 Advances of reactor core and fuel assembly
(1) High burnup fuel design (Step0, 1, 2)
(2) MOX fuel design
(3) Thermal-hydraulics design W-3, MIRC-1, NFI-1 correlations Subchannel analysis codes: THINC, COBRA-3C DNBR, MDNBR

3.3 Advances of reactor core and fuel analysis RELAP analysis, etc.

4. Plant Life Management and Maintenance Technologies

4.1 Regular inspection and inspection technologies

4.2 Preventive maintenance technologies

4.3 Reduction of radiation exposure

4.4 Protection and prediction technologies for erosion corrosion

5. PWR Innovations

5.1 Next Generation PWR

5.2 Small PWRs

5.3 US-APWR

5.4 AP1000

5.5 ATMEA1

5.6 Power uprate in PWR