7th INPRO Dialogue Forum on Sustainability of Nuclear Energy Systems Based on Evolutionary Reactors

  International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

​​19-22 November 2013 | IAEA Headquarter, Vienna, Austria

The INPRO Dialogue Forum brings together nuclear technology holders and nuclear technology users and other stakeholders from interested Member States to discuss issues related to sustainable nuclear energy development and deployment. The forum provides a unique opportunity with a number of vendors of evolutionary power reactors presenting exemplary INPRO Methodology assessments of their reactor designs.

The purposes of the 7th INPRO Dialogue Forum are to:

• Familiarize Member States with the INPRO methodology, with a focus on the sustainability assessment of nuclear energy systems (NESs) and on supporting long range and strategic planning for a successful nuclear power programme;
• Discuss the assessment of evolutionary nuclear reactors in the areas of safety;
• Discuss case studies and lessons learned in relation to, as well as support for, ongoing and future projects on national Nuclear Energy System Assessments (NESAs); and
• Discuss the salient features of evolutionary nuclear reactors that are relevant to the sustainability of an NES, and the important role of vendors in a NESA — particularly in providing necessary design data and information to support the assessment.

Report

• Report of Dialogue Forum

Working Documents

• Terms of Reference
• Agenda

Presentations

Session 1: Opening and IAEA/INPRO Presentations

• Opening remarks
  Alexander V. Bychkov, DDG-NE, IAEA
• Overview of INPRO project
  Z. Drace, INPRO Group Head, IAEA
• Program Overview and Objectives
  Juergen Kupitz, Chairman
• INPRO Methodology for Sustainability Assessment of Nuclear Energy System (NES)
  J. R. Phillips, INPRO, IAEA
• Safety Assessment and NPP Design Requirements
  H. Khartabil, NSNI, IAEA
• INPRO Methodology Requirements on Safety of Nuclear Reactors
  A. Korinny, INPRO, IAEA

Session 2: Vendors’ Presentations

 Vendor 1: Mitsubishi on APWR- Sumio Fujii, Tesushi Yuasa (Japan)

• Overview of Mitsubishi Advanced PWR
• Report on the Assessment of Mitsubishi Advanced PWR by INPRO Methodology

• Part 0. Assessment items selected for 7th Dialogue Forum
• Part 1. Operational Safety Margins in Design of APWR
• Part 2. Reactor Vessel Manufacturing and Welding of APWR
• Part 3. Simplicity and Reliability in Safety System Design of APWR
• Part 4. Reliability Data of Equipment and CDF of APWR
• Part 5. Detection of Anomalous Conditions and Safety Analysis of APWR
• Part 6. Integrated Full Digital I&C System and Advanced Operator Console of APWR

• Advanced PWR by Mitsubishi Heavy Industries

 Vendor 2: Rosatom on AES-2006/MIR.1200- Mikhail Bykov, Denis Kolchinsky (Russia)

• AES-2006 -New Design with VVER Reactor and INPRO Methodology
• Margins and Robustness: Design Solutions Providing the V-491 Reactor Plant Reliability
• Safety System of Reactor Plant V-491 and Safety Analyses Results
• Principles Providing Safety of the V-491 Type Reactor
• Release Into Containment in AES-2006 Design
• Independence of DID Levels in AES-2006 Design

Vendor 3: GE Hitachi Nuclear Energy International on ABWR- Kenichi Yasuda (Japan), James A. Beard (USA)

• Overview of ABWR Safety Issues
• Reliability and Autonomy of ABWR Safety Functions
• Improving the Operational Response of the ABWR
• Frequency Reduction and Accident Management in the ABWR
  
• Reducing the Operational Doses in the ABWR
  
• Manufacturing and Construction Improvements
  

Vendor 4: KEPCO on APR1400- Jong Tae Seo, Han Gon Kim (Korea)

• Overview of APR1400 Design
• I&C and Inherent Characteristics
• Reliability of Engineered Safety Features
• In-Plant Severe Accident Management
• Design Characteristics of APR1400 Safety Injection System: RD&D and Scaling
• Code Validation for APR1400 LBLOCA Analysis

Vendor 5: Candu Energy on EC6- Albert G. Lee, Sabina Boyle (Canada)

• Application of INPRO Comparative Assessment for Enhanced CANDU 6 ®
  Pertaining to Lessons Learned from the Fukushima Dai-ichi Nuclear Event
• Evolution of EC6 design from CANDU 6
• INPRO Safety Assessment of EC6 Safety Margins
• INPRO Safety Assessment of EC6 Robustness
• INPRO Safety Assessment of EC6 Safety Features
• INPRO Safety Assessment & EC6 Safety Goals
• Assessment Document for Application of INPRO Assessment for Enhanched CANDU 6

Vendor 6: GE Hitachi Nuclear Energy International on ESBWR- Gary L. Miller, James A. Beard (USA)

• Overview of ESBWR Safety Features
• Simplicity of ESBWR Passive Safety
• Redundancy and Reliability of Passive Safety Features
• Risk-Informing ESBWR Design with PSA
• ESBWR Severe Accident Prevention and Mitigation
• Confidence in ESBWR Safety Features

Vendor 7: AREVA on EPR design- Franck Lignini (France)

• Presentation of the EPR reactor
• Robustness of Design Part 1: Margins and Simplicity of Design
• Robustness of Design Part 2: Quality of Manufacture and Construction, Quality of Materials, and Redundancy of Systems
• Robustness of Design Part 3: Robustness against External Hazards
• Release into the Containment: Major Release, Processes, and Accident Management
• Occupational Dose
  

Session 3: Closing

• Discussion, Q&A
• Statements from Member States
• Meeting Summary
  
• Closing Remarks