Key Emerging Issues and Recent Progress Related to Structural Materials Degradation

(LCC8 AR)
This Report discusses the highlights from the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, which was held in Colorado Springs in August 2011. Over 150 papers were published at this conference and covered diverse topics touching on specific degradation modes in various alloys.

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Key Results From Recent Conferences on Structural Materials Degradation in Water Cooled Reactors

This report reviews the key papers published in the following conferences:

  • The 14th International Conference on “Environmental Degradation of Materials in Nuclear Power Systems”, Virginia Beach, USA, August 24–28, 2009.
  • The Fontevraud 7 Conference “Contribution of Materials Investigations to Improve the Safety and Performance of LWRs”, Avignon, France, September 26–30, 2010.
  • Jubilee day seminar on “Stress Corrosion Cracking of Nickel Base Alloys at CEA – Coriou Effect”, Saclay, France, January 26, 2010.

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Hot Cell Post-Irradiation Examination Techniques for Light Water Reactor Fuels

(ZIRAT19/IZNA14 STR)
Hot Cell Post-Irradiation Examination Techniques for Light Water Reactor Fuels The growing operational demands on nuclear fuel, such as longer fuel cycles, higher burnups, and use of transient regimes, call for more robust fuel designs and more radiation resistant materials. Implementation of new materials and fuel designs that are able to meet these more challenging conditions requires adequate operational feedback and practical verification of models for prediction of fuel behavior. Post-irradiation examinations (PIE) provide fuel vendors and nuclear utilities with data on how newly developed or established materials withstand normal operating conditions in new environments. Post-irradiation examinations are largely carried out at a Hot Cell Laboratory where irradiated fuel rods and other bundle hardware can be received, handled, examined, and tested. The investigation results provide information for fuel improvement and, thereby, can potentially enhance operating efficiency and reliability. The objectives of the hot cell examination of failed and sound sibling rods are to; characterize the fuel rod conditions associated with failure, identify the fuel failure mechanism, and provide insight into the root cause of the failures. The objectives of the hot cell examination of the fuel bundle hardware vary with the component being examined. The hot cell examinations/testing include a number of tasks selected to address these objectives using available hot cell capabilities. This Special Topic Report provides an overview about the status of post-irradiation examination (PIE) and inspection techniques for nuclear fuel and their applications for analysis of material degradation during fuel operation in a reactor core. Emphasis is given to advanced non-destructive and destructive PIE techniques applied to LWR fuel rods and bundle hardware. The objective of this STR is to provide this knowledge.

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Dry Storage Handbook

This handbook contain a technical assessment of the expected performance of spent nuclear fuel (SNF) during extended dry-storage time periods and the condition of such fuel at the end of dry storage.

The principal focus of the reviews is on SNF and the effects of dry storage rather than on dry-storage containers and the related storage facilities. The objective is to provide background information on the likely behavior of materials comprising water reactor fuel assemblies and on the performance of integral assemblies under conditions typical of dry storage for extended intervals of time.

In brief, the technical assessment supports a conclusion that, although technical issues have been postulated with regard to long-term storage, there are no high-risk concerns with the extension of dry storage to long times; with proper planning and implementation.

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Fuel Fabrication Process Handbook Rev 1 (FFPH)

The objective of the Fuel Fabrication Process Handbook is to provide guidance for a cost effective audit which uses audit time on areas which are most likely to affect the performance of the PWR/VVER and BWR fuel. The FFPH focuses on a “Process Audit” procedure, the audit of the fabrication process parameters for making high quality fuel. The FFPH provides the “what, why and how” to look at in an audit by:

  • Listing the generic fabrication process steps for all components and their assembly (what to look for).
  • Identifying important audit points and the attendant potential effect of deviations on performance (why to look).
  • Assess the fabrication and QC process control at critical points (how to look).

This Handbook is an updated and expanded version of the previous FFPH Handbook published in 2005. More than 35 organisations worldwide bought this Handbook. The expansion constitutes two sections on Statistical Quality Control and Software Quality Assurance. Statistical QC is a vital part of process control, the establishment of sampling plans and the qualification of inspection methods. The QA of software is important for auditing the software for the expanding automation of fabrication methods.

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Control Assembly Technology Report (FMTR Volume III)

The Report on Control Assembly Technology which constitutes Volume III of the series of Fuel Material Technology Reports (FMTRs) will be available during the Spring of 2014. It describes the designs, manufacturing, performance and issues related to BWR/PWR/VVER/CANDU Control Assemblies with Ag-In-Cd (AIC), B4C, Hf absorber materials and stainless steel structural materials.

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Fuel Material Technology Report (FMTR) – Volume IV

The primary objective of this volume of the Fuel Material Technology Report, FMTR Vol. IV, is to provide guidance in improving fuel reliability. To reach this objective, various Poolside and Hot Cell Examinations techniques may be used. A good knowledge of the pros- and cons- of the different techniques can guide the utility or fuel vendor to select the most cost efficient techniques for their specific goals. A second objective of this Report is to document this knowledge in a form which can be updated as new information, and methods become available.

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Fuel Material Technology Report (FMTR) – Volume II

In this second volume of the Fuel Material Technology Report, the following topics for different water cooled type reactors are covered:

  • Effect of radiation on the various fuel assembly materials as well as the interaction between materials and cooling water chemistry in this radioactive environment.
  • Water chemistries in different reactor types
  • Fuel design criteria and operating limits
  • Fuel performance during Loss Of Coolant Accidents and Reactivity Initiated Accidents
  • Fuel performance during intermediate storage
  • Trends and potential burnup limitations

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