Structural Alloys for Nuclear Energy Applications

Robert Odette, Steven Zinkle

• Publisher: Elsevier
• Year: 2019
• ISBN:
  9780123973498
• Topic: Technik & Maschinenbau
• Subtopic: Bergbautechnik

High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk.

Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management.

• Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities.
• Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors.
• Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.

Chapter 1

Overview of Structural Materials in Water-Cooled Fission Reactors

Jeremy T. Busby Oak Ridge National Laboratory, Oak Ridge, TN, United States

Abstract

Nuclear power currently provides a fraction of non-carbon-emitting power generation in the United States and around the world. The existing fleet of water-cooled reactors continues to improve on operations and reliability, as ensuring public safety and environmental protection is a prerequisite, whether water reactor, advanced reactor, or fusion. Materials are important during all phases of a reactor's lifetime and must perform reliably for their entire expected lifetime. Unfortunately, nuclear reactors of all designs present a challenge for component service and material performance, as exemplified in water reactors. Components within a reactor must tolerate the harsh environment of high-temperature water, stress, vibration, and, for those components in the reactor core, an intense neutron field. Degradation of materials in this environment can lead to reduced performance and, in some cases, sudden failure. This chapter will provide an overview of the key water reactor designs, their features, and materials of construction. In addition, this chapter will introduce some of the key degradation modes facing materials for nuclear power reactors, including irradiation effects and corrosion. Finally, this chapter will provide an introduction to the key materials of construction, their use, and key characteristics.

Keywords

Nuclear power reactors; Water-cooled reactors; Irradiation effects; Corrosion; Environmentally assisted degradation; Zirconium; Stainless steel; Low-alloy steel; Ni-based alloys

Chapter Outline

• 1.1 Introduction
• 1.2 The Lwr Reactor Environment and Key Modes of Degradation
  • 1.2.1 Thermal Aging and Fatigue
  • 1.2.2 Irradiation
  • 1.2.3 Water Environment
• 1.3 Overview of Key Materials of Construction for LWR Applications
  • 1.3.1 Zirconium-Based Alloys
  • 1.3.2 Austenitic Stainless Steels
  • 1.3.3 Cast-Austenitic Stainless Steels
  • 1.3.4 Ni-Base Alloys
  • 1.3.5 Low-Alloy Steels
• References

1.1 Introduction

Nuclear power currently provides a significant fraction of non-carbon-emitting power generation in the United States and around the world. According to the Nuclear Energy Institute's latest figures, the 99 operating light water reactors (LWRs) in the United States operate with a capacity of 99,300 MW. In 2016, this fleet generated over 800,000 GWh, representing 19.7% of the US electrical consumption [1]. Cumulatively, the 449 operating reactors represent 11% of the world's electrical generation and consumption [2]. The distribution of nuclear power plants is shown in Fig. 1.1. The nuclear generation capacity for each country is listed by country in Table 1.1. In 2016, 13 countries received over a quarter of their energy via nuclear power. Clearly, nuclear energy is a key resource for today's world.

Fig. 1.1 Distribution of operating nuclear power reactors around the world [2]. From IAEA Power Reactor Information System (PRIS), https://www.iaea.org/pris/. Used with permission from IAEA.

Table 1.1

Summary of Nuclear Generating Capacity Around the World [1]

	As of April 2017		2016
Country	Number of Nuclear Units	Nuclear Capacity (MW)	Nuclear Generation (GWh)	Nuclear Fuel Share (%)
Argentina	3	1632	7677.4	5.6
Armenia	1	375	2194.9	31.4
Belgium	7	5913	41,430.5	51.7
Brazil	2	1884	14,970.5	2.9
Bulgaria	2	1926	15,083.5	35.0
Canada	19	13,554	95,650.2	15.6
China	36	31,384	197,829.0	3.6
Czech Republic	6	3930	22,729.9	29.4
Finland	4	2764	22,280.1	33.7
France	58	63,130	386,452.9	72.3
Germany	8	10,799	80,069.6	13.1
Hungary	4	1889	15,183.0	51.3
India	22	6240	35,006.8	3.4
Iran, Islamic Republic of	1	915	5924.0	2.1
Japan	43	40,290	17,537.1	2.2
Korea, Republic of	25	23,077	154,306.7	30.3
Mexico	2	1552	10,272.3	6.2
Netherlands	1	482	3749.8	3.4
Pakistan	4	1005	5438.9	4.4
Romania	2	1300	10,388.2	17.1
Russia	37	26,528	184,054.1	17.1
Slovakia	4	1814	13,733.4	54.1
Slovenia	1	688	5431.3	35.2
South Africa	2	1860	15,209.5	6.6
Spain	7	7121	56,102.4	21.4
Sweden	10	9740	60,647.4	40.0
Switzerland	5	3333	20,303.1	34.4
Taiwan, China	6	5052	30,461.0	13.7
United Kingdom	15	8918	65,149.0...

Table of contents

• Cover image
• Title page
• Table of Contents
• Copyright
• Contributors
• Preface
• Chapter 1: Overview of Structural Materials in Water-Cooled Fission Reactors
• Chapter 2: Overview of Reactor Systems and Operational Environments for Structural Materials in Gen-IV Fission Reactors
• Chapter 3: Overview of Reactor Systems and Operational Environments for Structural Materials in Fusion Reactors
• Chapter 4: Research Tools: Microstructure, Mechanical Properties, and Computational Thermodynamics
• Chapter 5: Radiation and Thermomechanical Degradation Effects in Reactor Structural Alloys
• Chapter 6: Corrosion Issues in Current and Next-Generation Nuclear Reactors
• Chapter 7: Zirconium Alloys for LWR Fuel Cladding and Core Internals
• Chapter 8: Austenitic Stainless Steels
• Chapter 9: Ni-Based Alloys for Reactor Internals and Steam Generator Applications
• Chapter 10: Low-Alloy Steels
• Chapter 11: Ferritic and Tempered Martensitic Steels
• Chapter 12: Nano-Oxide Dispersion-Strengthened Steels
• Chapter 13: Refractory Alloys: Vanadium, Niobium, Molybdenum, Tungsten
• Index