ANT International Educational Seminars 2014

Boosting your Excellence through Knowledge and Training
ANT International
Educational Seminars
2014
ANT International is specialised in providing expert training and knowledge in the areas of
nuclear fuel, structural materials and water chemistry in water cooled nuclear power plants.
The major products and services which we provide in these three areas are:
• Educational Seminars
• Handbooks & Reports related to the above Seminars
The objective of the Seminars is to provide engineers and managers the necessary background information to:
• Increase the understanding of materials and reactor water behaviour related to successful
core operation while keeping personnel radiation exposure low and,
• Ensure the integrity of structural materials.
This brochure describes the different Seminars ANT International plans to provide in Spain
and USA in February–March, 2014.
Contents
Fuel
Materials in Light Water Reactors (ANTIA*)
1. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
2. Fuel material performance during normal operation
and
anticipated operational occurrences . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
3.Interim storage and transport of spent fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
4.Fuel material performance during design basis accidents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
Fuel Design Review Seminar . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
Fuel Fabrication Seminar . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
Zirconium Alloy Technology Seminar (ZIRAT) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
Materials Degradation in Light Water Reactors (ANTIA*) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
Plant Chemistry and Corrosion (ANTIA*)
PWR/VVER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
BWR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13
LWR Chemistry and Component Integrity Seminar (LCC) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
* ANT International Academy (ANTIA) is an educational programme for staff desiring both a bird’s eye
view and a comprehensive introduction and overview of the following topics: Fuel materials, BWR/PWR/
VVER plant chemistry and structural material degradation. More information
Fuel Materials in Light Water Reactors
The objective of the Fuel Materials Seminars is to provide engineers/managers with the
necessary background information to understand more complicated fuel material information.
The objective is met by four different seminars. The first Seminar is an introduction to
Fuel Material while Seminars No. 2–4 are in-depth seminars on specific topics.
1.Introduction
TOPICS COVERED:
• Overview of plant chemistries and rational for its use in PWRs/VVERs and BWRs
• Mechanical, T/H and nuclear fuel assembly design
• Manufacturing of fuel assembly and its components as well as UO2 and Zr alloys
• Effects of irradiation on fuel assembly materials and water (radiolysis)
• Reactor safety, operation restrictions, fuel performance codes, treatment of
uncertainties, margins
• Overview of in-reactor fuel performance during normal operation, anticipated
operational occurrences, design basis accidents and interim dry storage
• High burnup/performance issues
LECTURERS:
Dr. Charles Patterson and Mr. Peter Rudling
DATE AND LOCATION:
February 4–7, 2014 at Sheraton Sand Key Resort in Clearwater Beach, Florida, USA
Additional information about the Seminar
Customer Feedback from Seminar in 2013:
“It’s a good overview of what is going on in the fuel and a good introduction
for people who are relatively “new” in the fuel business.”
T H E O VA N B L O O I S
Reactor Physics Section Leader, EPZ
“The seminar fitted my needs very well.”
M A R I O TOM E KOV I C
System Engineer in Chemistry, NEK
“Very thorough and broad coverage; excellent!”
T I NA KLASEN
Nuclear Fuel Technology Specialist, KKL, Axpo
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2. Fuel material performance during normal operation
and anticipated operational occurrences
TOPICS COVERED:
• Performance of Zr alloys
• Fuel reliability and consequences of fuel failures, methods to detect fuel failures during
operation and outage (poolside and hot cell)
• Secondary degradation of failed fuel
• Performance of UO2 and MOX
• Performance of stainless steel and nickel-base alloy fuel assembly components
LECTURERS:
Dr. Charles Patterson, Dr. Ronald Adamson and Mr. Peter Rudling
DATE AND LOCATION:
• March 4–7, 2014 in Europe at a location to be identified later
• February 2015 at Sheraton Sand Key Resort in Clearwater Beach, Florida, USA
Additional information about the Seminar
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3. Interim storage and transport of spent fuel
TOPICS COVERED:
• Spent Nuclear Fuel (SNF) Management in US, Europe and Japan
• Recent reviews and events on disposition of SNF, with emphasis on impacts on dry storage
• Existing dry-storage regulations
• Technical issues associated with extension of dry-storage time periods and potential
impacts on the existing dry-storage regulatory bases
• Existing transportation regulations, the regulatory bases that could be impacted by
extended dry-storage time periods, and the potential impacts on regulations
• General considerations for dry-storage systems
• Existing programs to determine open issues and address them
– Evaluation, testing, and surveillance programs
LECTURERS:
Dr. David Franklin, Dr. Charles Patterson and Mr. Friedrich Garzarolli
DATE AND LOCATION:
• February 13–14, 2014 at Sheraton Sand Key Resort in Clearwater Beach, Florida, USA
• March 13–14, 2014 in Europe at a location to be identified later
Additional information about the Seminar
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4. Fuel material performance during
design basis accidents
TOPICS COVERED:
• Reactor safety and kinetics
• Fuel behaviour during LOCA/RIA/seismic events
• LOCA/RIA/seismic testing
• Licensing criteria
• Modeling and computer codes
• Current issues
LECTURERS:
Dr. Charles Patterson, Dr. Gunnar Rönnberg and Mr. Peter Rudling
DATE AND LOCATION:
• February, 2015 in Europe at a location to be identified later
• February, 2016 in USA at a location to be identified later
Additional information about the Seminar
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Fuel Design Review Seminar
This Seminar provides a guide for reviewing and auditing the fuel design to assist in the
assurance that it will perform its design functions adequately.
TOPICS COVERED:
• Structures and components
• Audit Procedures
• Design Method Qualification
• Design QA System Audit
• Mechanical T/H and Nuclear Design Audits
• T/H Design Audit
• Nuclear Design Audit
• LOCA and RIA Audit
LECTURERS:
Mr. Alfred Strasser, Dr. Richard Collingham and Mr. Peter Rudling
DATE AND LOCATION:
February 13–14, 2014 at Sheraton Sand Key Resort in Clearwater Beach, Florida, USA
Additional information about the Seminar
Customer Feedback from Seminar in 2012:
“As a Safety Analysis Engineer in the process of cross training into
Core Design, this handbook is a must have. I also attended the tailored Seminar
for the Handbook during the Summer of 2012 at Diablo Canyon Nuclear Power Plant.
The Fuel Design Review Handbook is a very impressive and useful document.
The Seminar was a two day course which detailed out the various sections of the
handbook and allowed for input from all of the attendees. For me, it was a very
useful class and I would recommend it for any utility engineer that are
currently involved in core design or are considering it.”
M A L C O L M B . S M I T H P. E .
Safety Analysis/Reactor Engineering, Callaway Nuclear Plant
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Fuel Fabrication Seminar
The objective of the Fuel Fabrication Process Seminar 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 fuel.
TOPICS COVERED:
• Structure and Components of the Fuel Assembly
• Process Qualification
• Fuel and Fuel Pellet Fabrication
• Zirconium Alloy Component Fabrication
• Utility Audit Procedures
• Workshop
LECTURERS:
Mr. Alfred Strasser and Mr. Peter Rudling
DATE AND LOCATION:
March 13–14, 2014 in Europe at a location to be identified later
Additional information about the Seminar
Customer Feedback from Seminar in 2011:
“Peter and Al Strasser are experts in this field. Their book is superb and
the seminar was outstanding. I liked the seminar because it gave a quick insight
into the whole fabrication process in a day and a half. That’s a lot faster
than I could get through the book.”
M AT T K I R K L A N D
Principal Engineer, Reactor Engineering, Fermi 2 Nuclear Power Plant
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Zirconium Alloy Technology Seminar
(ZIRAT)
The overall objective of the ZIRAT Programme is to enable the nuclear utilities and
engineering organisations to gain increased understanding of fuel material behaviour related
to successful core operation, fuel performance during accident and interim dry storage
conditions. The Seminar is targeted towards more experienced engineers.
TOPICS COVERED:
• Mechanical Testing Procedures relevant to zirconium alloy components used in
commercial reactors
• High burnup and performance issues
• Fuel reliability
• Fuel (UO2 and MOX)
• Zr alloy corrosion and hydrogen pickup
• ZrO2 characteristics
• Zr alloy irradiation growth and creep
• Interim dry storage
LECTURERS:
Dr. Charles Patterson, Dr. Tahir Mahmood, Dr. Ronald Adamson, Mr. Peter Rudling,
Mr. Friedrich Garzarolli, Dr. Kit Coleman and Dr. David Franklin
DATE AND LOCATION:
• February 10–12, 2014 at Sheraton Sand Key Resort in Clearwater Beach, Florida, USA
• March 10–12, 2014 in Europe at a location to be identified later
Information on the ZIRAT Programme
Customer Feedback from Seminar in 2013:
“Great conference!”
LE I F M IC H EL SSON
Fuel Engineer, Nuclear Fuel, TVO
“An interesting seminar with very useful information and a close overview of the
state of art of nuclear fuel. I will recommend the seminar to my colleagues.”
I G N AC I O C O L L A Z O
Reload Safety Analyst, Iberdrola
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Materials Degradation in
Light Water Reactors
The objective of the Materials Degradation in LWRs Seminar is to provide engineers/
managers with the necessary background information to understand more complicated
plant corrosion and metallurgical information. Material issues related to carbon/low alloy/
stainless steels and nickel base alloys are covered.
TOPICS COVERED:
• Introduction and background to materials degradation
• Physical metallurgy of structural alloys
• Corrosion basics
• Water chemistry in nuclear plants
• Uniform, accelerated and localized corrosion
• Environmentally-assisted cracking of carbon/low alloy steels, austenitic and, Ni-base alloys
• Corrosion tests
• Corrosion mitigation
LECTURERS:
Dr. Peter Ford, Dr. Peter Scott and Dr. Pierre Combrade
DATE AND LOCATION:
• February 4–7, 2014 at Sheraton Sand Key Resort in Clearwater Beach, Florida, USA
• March 4–7, 2014 in Europe at a location to be identified later
Additional information about the Seminar
Customer Feedback from Seminar in 2013:
“The theoretical information was huge and amazing
as well as the knowledge of the speakers”
J E SUS H ER NA N DO PER EZ
Material Manager, Iberdrola
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Plant Chemistry and Corrosion
The objective of the Plant Chemistry and Corrosion Seminars is to provide chemists/
engineers/managers with the necessary background information to understand more
complicated plant chemistry information. There is one BWR and PWR seminar.
PWR/VVER Plant Chemistry and Corrosion
TOPICS COVERED:
• Materials and design selection
• Influence of Coolant Chemistry on Fuel Performance
• Plant Radiochemistry
• Reactor coolant system chemistry
• Secondary system chemistry and corrosion
• Decontamination
• Incoming goods, Materials specifications and control
• Laboratory quality control
• Makeup demineralized water preparation
LECTURERS:
Dr. Francis Nordmann, Dr. Suat Odar and Mr. Dewey Rochester
DATE AND LOCATION:
• February 4–7, 2014 at Sheraton Sand Key Resort in Clearwater Beach, Florida, USA
• March 4–7, 2014 in Europe at a location to be identified later
Additional information about the Seminar
Page 12 (15)
BWR Plant Chemistry and Corrosion
TOPICS COVERED:
• Designs and materials selection
• Water chemistry, electrochemistry and corrosion fundamentals
• Systems description
• Dose rate mitigation technologies
• IGSCC mitigation technologies
• Water chemistry specification, guidelines and action levels
• Plant operational chemistry and controls
• Water chemistry impacts on fuel
• Activation products and fission products
LECTURERS:
Dr. Samson Hettiarachchi and Dr. Robert Cowan
DATE AND LOCATION:
• February 4–7, 2014 at Sheraton Sand Key Resort in Clearwater Beach, Florida, USA
• March 4–7, 2014 in Europe at a location to be identified later
Additional information about the Seminar
Page 13 (15)
LWR Chemistry and
Component Integrity Seminar (LCC)
The objective of the LCC Seminar is to enable the nuclear utilities, engineering organizations,
reactor vendors and regulators to gain increased understanding of reactor water chemistry
related to a successful plant operation and continued integrity of Reactor Coolant System
(RCS) materials while keeping radiation exposure low.
The Seminar is targeted towards more experienced engineers.
TOPICS COVERED:
• Effect of WC on Zr alloy corrosion and HPU
• Environmental Degradation of Structural Materials
• Corrosion Fatigue
• Mechanical and design mitigation of various types of corrosion encountered in the
PWR primary circuit
• Enriched Boric Acid
• Behaviour of Co-58 and nickel in a high duty core
• Degradation of Concrete Structures in NPPs
• Colloids, Zeta Potential and Activity Transport
• ECP Monitoring in BWRs and PWRs
• Key plant chemistry information from International Conferences in 2013
LECTURERS:
Dr. Peter Ford, Dr. Peter Scott, Dr. Pierre Combrade, Dr. Francis Nordmann,
Dr. Suat Odar, Mr. Dewey Rochester, Dr. Sam Hettiarachchi, Dr. Robert Cowan and
Mr. François Cattant
DATE AND LOCATION:
March 10–12, 2014 in Europe at a location to be identified later
Information on the LCC Programme
Customer Feedback from Seminar in 2013:
“Very good seminar, especially for “beginners” in the field and a good opportunity
to meet experts and fellow colleagues from other plants.”
LENA JOH A NSSON
Axpo Chemistry Department
“The LCC Seminar has been very enjoyable and informative. It has broadened my understanding of many topics and has given me ideas/research to explore in the near future.”
J O H N MC G R A DY
Rolls-Royce sponsored EngD Student, University of Manchester
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www.antinternational.com
Office Address: Advanced Nuclear Technology International, Analysvägen 5, SE-435 33 Mölnlycke, Sweden.
Phone: +46 (0)31-88 16 00. Fax: +46 (0)31-88 16 01. [email protected] www.antinternational.com
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