In June 2020, the Nuclear Regulatory Commission (NRC) finalized Regulatory Guide (RG) 1.2361 for plants evaluating the rod ejection accident (or reactivity-initiated accident [RIA]). The regulatory change is an enhancement of the precursor (RG 1.772 ) requiring a more detailed transient analysis that cannot be completed in the old onedimensional (1D) kinetics analysis methodology.

In response to industry motivation to reduce the cost and effort associated with reload low power physics testing (LPPT) – particularly elimination of rod worth measurements – Westinghouse has developed a methodology to optimize post-refueling startup physics testing.

Westinghouse’s AXIOM® alloy is our next generation of fuel rod cladding material developed for demanding fuel duties and higher burnups. AXIOM cladding provides improved corrosion resistance and hydrogen pick-up performance, while maintaining excellent dimensional stability and superior resistance to aggressive coolant chemistry conditions.

The BEACON™ Core Monitoring System is an advanced core monitoring and support package that uses current instrumentation in conjunction with a three-dimensional (3-D), nodal analytical methodology for online measurement and analysis of 3-D power distributions. The system performs core monitoring, measurement data reduction, analysis, and follow and prediction.

BEACON™ 堆芯监测系统是一款先进的堆芯监测及支 持性软件包，该系统使用现有测量仪器，结合三维 (3D) 节点分析方法对三维功率分布进行在线测量及 分析。此系统可完成堆芯监测、测量数据处理、分 析、跟踪及预测。

Since 2013, debris-induced fuel failures have led to declining fuel performance industrywide as addressed in INPO Event Report 19-6. Not only do these failures lead to increased fission products in the reactor coolant system (RCS),

To improve the overall optical quality of underwater inspections, Westinghouse has developed an all-digital, high-definition, underwater inspection system to allow utilities to see what they have been missing.

Westinghouse has a proven tool to provide solutions to many common emergent and long-term utility concerns. Westinghouse’s CE Nuclear Transient Simulator (CENTS) code is a U.S. Nuclear Regulatory Commission (NRC) licensed best-estimate analysis code that can be used in a variety of pressurized water reactor (PWR) and boiling water reactor (BWR) applications.

Westinghouse developed the CE16NGFTM next generation nuclear fuel assembly for 16x16 Combustion Engineering nuclear steam supply system (CE-NSSS) style reactors to improve fuel performance, especially at high-duty operation, enhance fuel reliability and provide additional value to users through power upratings, improved operability and favorable fuel cycle economics.

Through its acquisition of ABB Combustion Engineering Nuclear Power in 2000 and its current KWN joint venture in Korea, Westinghouse supports the supply of 14x14 and 16x16 Control Element Assemblies (CEAs) for Combustion Engineering Nuclear Steam Supply System (CENSSS) plants, including those based on System 80 design technology. Westinghouse supplies all of the various full strength and part strength CEA design types used by the current operating fleet of CE-NSSS reactors.

Westinghouse Criticality Safety Services assess the margins to criticality, promoting safe and cost-effective storage, handling and transportation of pressurized water reactor (PWR) and boiling water reactor (BWR) nuclear fuel products. Criticality Safety Services provide explicit and complete analyses of fresh and spent nuclear fuel configurations, including extensive documentation and licensing support. All analyses are performed under the Westinghouse Quality Management System (QMS), providing verification and validation of all analysis and documentation activities.

Westinghouse’s next-generation Customer Collaboration Center (C3) takes the work and worry out of managing engineering servers for your Westinghouse-licensed technologies. Users are free to create a specialized computing environment on systems that conform to strict Westinghouse standards, thereby producing dependable, reliable and consistent results.

The enhanced performance rod cluster control assembly (EP-RCCA™) was developed to provide enhanced performance relative to previous control rod designs through the selection of materials and surface treatment that enhance the product’s resistance to wear and irradiation. The materials were selected with the intent to perform well with regard to corrosion and dimensional stability over the EP-RCCA design lifetime.

FUELDUTYDRV (FDD) is a best-estimate fuel component analysis tool that can process physics data, thermal-hydraulic (TH) analysis codes and mechanical data for fuel performance assessment of any and all fuel rods in the core.

As its name implies, the state-of-the-art FULL SPECTRUM™ LOCA (FSLOCA™) evaluation model can analyze the full spectrum of LOCA break sizes with improved capability and analysis results compared to prior LOCA technologies. The FSLOCA evaluation model is NRC-approved for application to Westinghouse 3-loop and 4-loop PWRs. Extensions of the methodology to Westinghouse 2-loop PWRs, plants equipped with direct vessel injection, and CE PWRs are ongoing such that the methodology will soon be NRC approved for all Westinghouse and CE PWR designs.

Westinghouse’s Integral Fuel Burnable Absorber (IFBA) fuel pellet has revolutionized PWR nuclear reactor fuel management loading patterns and has enabled highly improved fuel cycle economics. Westinghouse is now building on the success of our flagship IFBA product with IFBA/Gad hybrid fuel assemblies that facilitate longer (24-month ) cycles while providing similarly improved fuel cycle cost (FCC) savings.

Pellet clad interaction (PCI) is a serious concern for operation of nuclear power plants under transient conditions such as those that occur during startup, temporary down power for maintenance activities, load follow or dropped rod recovery. Under these conditions, fuel failure can occur if the core is ramped too quickly. However, the definition of “too quickly” depends on fuel operating history; thus, if a single “rule of thumb” ramp rate is used it will be necessarily conservative and the plant will be delayed in getting maximum power on to the grid.

The Westinghouse Next-Generation Rod Cluster Control Assembly (NG-RCCA™) has been developed to provide further performance enhancements and increased longevity of the control rod assembly. The NG-RCCA builds upon proven and reliable Enhanced-Performance Rod Cluster Control Assembly (EP-RCCA™) design, which has had a service history of more than 30 years and more than 3,000 assemblies delivered globally to a wide variety of plants designs.

The Westinghouse Advanced Nodal Code (ANC) is a highly accurate and efficient two-energy group, three-dimensional (3D) core simulator code. It uses the nodal expansion method for the nodal coupling coefficient, a group theory for pin power recovery, and the equivalence theory for homogenization.

Operation of a nuclear power plant requires an accurate and robust safety analysis. New regulatory requirements, advancements in fuel designs, plant upgrades supporting long-term operations and license extensions drive the need for advanced safety analysis codes and methods.

Westinghouse core designers spend considerable time and effort developing high-performing loading patterns (LPs). However, redesigns are sometimes necessary, and even well-designed loading patterns can be adversely affected by fuel issues. When this occurs, months worth of design effort must be compressed into weeks or even days. Utilities can incur substantial costs waiting for a new loading pattern to be developed, analyzed and verified before continuing with the reload.

Over the past 40 years, Westinghouse educational specialists and subject matter experts have provided training in fuel, services, technology, plant design and equipment to utility and industrial customers in the worldwide commercial nuclear electric power industry. Our passion for the nuclear industry, its plants and its people allow Westinghouse to leverage learning for global success by developing relationships that allow a better understanding of utility cultures which, in turn, results in nuclear safety and performance improvement.

Optimized ZIRLO™ High-performance Fuel Cladding Material represents an evolutionary development of Westinghouse’s ZIRLO® High-performance Fuel Cladding Material.

Industry studies indicate that the reactor pressure vessel may be a limiting component with respect to attaining the desired life and life extension (i.e., long-term operation/subsequent [second] license renewal [LTO/SLR]) for many nuclear power plants. The primary reactor vessel life attainment issue is concerned with the prevention of nonductile failure of the reactor vessel welds, which are subject to neutron radiation-induced embrittlement effects. For those vessels where this concern exists during their anticipated operational life, the implementation of neutron flux reduction programs can play a significant role in attaining desired reactor lifetimes. Because fluence impacts to these welds build up over time, effective fluence reduction requires implementing a program as early as possible to minimize the amount of incremental fluence reduction needed in each future cycle after program implementation (see graph).

Westinghouse has more than 40 years of experience in design and manufacture of nuclear fuel assemblies that help utilities achieve exceptional fuel reliability and performance in today’s operating and commercial environment. The 17x17 robust fuel assembly (RFA-2) has demonstrated excellent fuel performance worldwide.

西屋电气公司在核燃料组件的设计及制造方面拥有40 多年丰富经验，在当今的电厂运行和商务环境中，这 些丰富经验及燃料设计可以帮助核电厂实现卓越的燃料可靠 性及性能。坚固的 17x17 燃料组件 (RFA-2) 已经 在世界范围内展示出非凡的燃料性能。

The Westinghouse Double Encapsulated Secondary Source Assemblies (SSAs) were developed to provide an adequate source of neutrons for reload core fuel movement reactivity monitoring and subsequent cycle startups while further protecting the source material from erosion to the primary coolant system. The double encapsulated SSA design is the direct result of Westinghouse applying knowledge learned from over 4500 reactor-years of operational performance experience of the previous single encapsulated SSA design

Industry studies indicate that the reactor pressure vessel may be a limiting component with respect to attaining the desired life and life extension, i.e., Long Term Operation (LTO) / Subsequent (Second) License Renewal (SLR), for many nuclear power plants. The primary reactor vessel life attainment issue is concerned with the prevention of non-ductile failure of the reactor vessel welds, which is subject to neutron radiation-induced embrittlement effects.

The TracWorks® fuel data management system is a source of comprehensive, and integrated fuel and component-related information for a nuclear plant’s operators, engineers and administrators. The TracWorks system provides life-cycle tracking, data management and reporting for all fuel assemblies or bundles and components for both pressurized water reactor (PWR) and boiling water reactor (BWR) units.

Westinghouse has performed loss of coolant accident mass and energy release calculations (LOCA M&E calculations) for nearly 40 years. Westinghouse has significantly improved its capabilities with the development of the WCOBRA/TRAC LOCA M&E methodology.

Westinghouse has developed advanced fuel assembly features and supporting PWR core component products to improve fuel performance, enhance fuel cycle economics and support extended (24-month) cycle length operation. One such PWR core component is a Wet Annular Burnable Absorber (WABA) assembly, a discrete burnable absorber component used in some WNSSS reactor core fuel cycle loading strategies.