ZoomDetails

High Burnup Fuel Design Issues and Consequences

Fuel Material, Other Issues

(ZIRAT17/IZNA12 STR)
One of the major present challenges to nuclear energy lies in its commercial competitiveness. To stay competitive, the industry needs to maximize the availability and capacity factors of nuclear power plants while reducing maintenance and fuel cycle costs and enhancing safety. Extended burnup is one of the methods applied to meet these objectives. There are a number of issues related to normal operation, anticipated operation occurrences, design basis accidents and dry storage that need resolution to be able to successfully implement extended burnup. This special topic reviews the potential consequences of increased burnup on fuel. Recommendations are also given on how to remedy the high burnup issues.

DOWNLOAD SAMPLE

ZoomDetails

High Strength Nickel Alloys for Fuel Assemblies

Fuel Material, Other Issues

(ZIRAT17/IZNA12 STR)
This Report is a comprehensive review and evaluation of the high strength nickel alloys (625, 718, X-750 and A286) used for PWR/VVER and BWR fuel assembly components. These alloys have been used for spacer grids, bolts and springs since the start of the LWR industry. The report concentrates on the good performance record as well as a description of the reported failures, their causes and remedies. The relationship of various heat treatments to the microstructures and their corrosion resistance are discussed.

DOWNLOAD SAMPLE

ZoomDetails

Performance Evaluation of New Advanced Zr Alloys for PWRs/VVERs

Fuel Material, Other Issues

(ZIRAT16/IZNA11 STR)
To meet the current situation with more aggressive reactor environments, a large number of zirconium alloys have been and are being developed. The objective of this Report is to ensure that the new Zirconium Alloys performs satisfactory during normal operation, Anticipated Operational Occurrences (AOOs), postulated accidents and intermediate dry storage.

DOWNLOAD SAMPLE

ZoomDetails

Welding of Zirconium Alloys

Fuel Material, Other Issues

(ZIRAT12/IZNA7 STR)
The welding of Zirconium Alloy components is one of the most critical manufacturing processes of Nuclear Reactor fuel. Small amounts of contamination resulting from inadequate cleanliness or from poor atmospheric control during welding may lead to diminished corrosion resistance of the weld and in severe cases to weld failure. Other weld defects such as piping, pore formation or insufficient weld penetration may also result in costly fuel failures. This Report describes the different welding processes used for the various fuel assembly components. A comprehensive discussion of welding Quality Management is included.

DOWNLOAD SAMPLE

ZoomDetails

Impact of Irradiation on Material Performance

Fuel Material, Other Issues

(ZIRAT10/IZNA5 STR)
Reactor neutron irradiation dramatically affects the properties and performance of all the materials in the reactor core. This report focuses on the behaviour of zirconium alloys used for the main structural components in the fuel bundle and should provide a solid understanding of the role that irradiation plays in component performance. This report is a complementary companion to the Structural Behaviour of Fuel Components (ZIRAT10/IZNA5 STR)

DOWNLOAD SAMPLE

ZoomDetails

High Burnup Fuel Issues, Their Most Recent Status

Fuel Material, Other Issues

(ZIRAT8/IZNA3 STR)
With increased burnup, processes going on inside a nonfailed fuel rod decrease pellet density, lower the fuel melting temperature and thermal conductivity, increase the fission gas release. Also, a high burnup structure is formed at pellet average burnups in excess of about 50 MWd/kgU This volume I of the report describes the processes going on inside a nonfailed fuel rod during normal operation. The associated volume II of the report describes the corresponding information during accident conditions (RIA and LOCA).

DOWNLOAD SAMPLE

ZoomDetails

Processes Going on in Nonfailed Rod During Normal Operation — Vol. I

Fuel (UO2 and MOX) Performance, Fuel Material

(ZIRAT15/IZNA10 STR)
With increased burnup, processes going on inside a nonfailed fuel rod decrease pellet density, lower the fuel melting temperature and thermal conductivity, increase the fission gas release. Also, a high burnup structure is formed at pellet average burnups in excess of about 50 MWd/kgU This volume I of the report describes the processes going on inside a nonfailed fuel rod during normal operation. The associated volume II of the report describes the corresponding information during accident conditions (RIA and LOCA).

DOWNLOAD SAMPLE