Transient Analysis Needs for Generation IV Reactor Concepts

The importance of nuclear energy as a vital and strategic resource in the U. S. and world’s energy supply mix has led to an initiative, termed Generation IV by the U.S. Department of Energy (DOE), to develop and demonstrate new and improved reactor technologies. These new Generation IV reactor concepts are expected to be substantially improved over the current generation of reactors with respect to economics, safety, proliferation resistance and waste characteristics. Although a number of light water reactor concepts have been proposed as Generation IV candidates, the majority of proposed designs have fundamentally different characteristics than the current generation of commercial LWRs operating in the U.S. and other countries. This paper presents the results of a review of these new reactor technologies and defines the transient analyses required to support the evaluation and future development of the Generation IV concepts. The ultimate objective of this work is to identify and develop new capabilities needed by INEEL to support DOE’s Generation IV initiative. In particular, the focus of this study is on needed extensions or enhancements to SCDAP/RELAP5/3D code. This code and the RELAP5-3D code from which it evolved are the primary analysis tools used by the INEEL and others for the analysis of design-basis and beyond-design-basis accidents in current generation light water reactors.

Download Full-text

Safety evaluation report related to the Department of Energy`s proposal for the irradiation of lead test assemblies containing tritium-producing burnable absorber rods in commercial light-water reactors. Project Number 697

10.2172/491562 ◽

1997 ◽

Author(s):

Keyword(s):

Safety Evaluation ◽

Department Of Energy ◽

Light Water Reactors ◽

Evaluation Report ◽

Light Water ◽

Burnable Absorber ◽

Water Reactors

Download Full-text

Fabrication and Mechanical Aspects of Using FeCrAl for Light Water Reactor Fuel Cladding

Volume 6B: Materials and Fabrication ◽

10.1115/pvp2019-93128 ◽

2019 ◽

Cited By ~ 1

Author(s):

Raul B. Rebak ◽

Shenyan Huang ◽

Michael Schuster ◽

Steve J. Buresh ◽

Evan J. Dolley

Keyword(s):

High Strength ◽

Future Generation ◽

Department Of Energy ◽

Advanced Technology ◽

Severe Accident ◽

Light Water ◽

The Us ◽

Water Reactors ◽

Accident Conditions ◽

Welding Processes

Abstract General Electric (GE) is working with the US Department of Energy (DOE) to develop advanced technology fuel (ATF) for light water reactors (LWR) that will have enhanced tolerance to failure under severe accident conditions. The development of materials for the current fuel is aimed at Generation III LWR but findings may be extended to future Generation IV reactors. One of the concepts pursued by GE is to use iron-chromium-aluminum (FeCrAl) or IronClad for the cladding due to its outstanding resistance to reaction with air and steam at temperatures higher than 1000°C. Ferritic FeCrAl alloys have been used for almost nine decades in the industry, but never in nuclear applications, therefore its fabrication and mechanical aspects for nuclear use needs to be evaluated. Results show that billets of FeCrAl can be produced via traditional melting and using powder metallurgy, and these billets can later be processed to high strength full length cladding tubes having less than half a millimeter wall thickness. The tubes can be joined to the caps via several welding processes.

Download Full-text

KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors

Kerntechnik ◽

10.3139/124.110687 ◽

2016 ◽

Vol 81 (2) ◽

pp. 145-148

Author(s):

V. Sanchez ◽

A. Miassoedov ◽

M. Steinbrück ◽

W. Tromm

Keyword(s):

Light Water Reactors ◽

Light Water ◽

Design Basis ◽

Water Reactors

Download Full-text

FeCrAl Alloys for Accident Tolerant Fuel Cladding in Light Water Reactors

Volume 6B: Materials and Fabrication ◽

10.1115/pvp2016-63162 ◽

2016 ◽

Cited By ~ 3

Author(s):

Raul B. Rebak ◽

Kurt A. Terrani ◽

Russ M. Fawcett

Keyword(s):

Fuel Assembly ◽

Department Of Energy ◽

Normal Operation ◽

Fuel System ◽

Light Water Reactors ◽

Light Water ◽

Oak Ridge ◽

Operation Conditions ◽

Fecral Alloys ◽

Water Reactors

The goal of the U.S. Department of Energy (DOE) Accident Tolerant Fuel Program (ATF) for light water reactors (LWR) is to identify alternative fuel system technologies to further enhance the safety of commercial nuclear power plants. An ATF fuel system would endure loss of cooling in the reactor for a considerably longer period of time than the current systems. The General Electric (GE) and Oak Ridge National Laboratory (ORNL) ATF design concept utilizes an iron-chromium-aluminum (FeCrAl) alloy material as fuel rod cladding in combination with uranium dioxide (UO2) fuel pellets currently in use, resulting in a fuel assembly that leverages the performance of existing/current LWR fuel assembly designs and infrastructure with improved accident tolerance. Significant testing was performed in the last three years to characterize FeCrAl alloys for cladding applications, both under normal operation conditions of the reactor and under accident conditions. This article is a state of the art description of the concept.

Download Full-text

Safety and Design Principles for Use in a Risk-Informed, Technology-Neutral Design and Licensing Framework for New Nuclear Plants

Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition ◽

10.1115/icone17-75171 ◽

2009 ◽

Author(s):

Jim Chapman ◽

Stephen M. Hess

Keyword(s):

Design Principles ◽

Current Generation ◽

Light Water ◽

Integrated Framework ◽

Nuclear Plants ◽

Underlying Basis ◽

Water Reactors ◽

Near Term ◽

Reactor Types ◽

And Performance

The regulatory framework for the current generation of operating plants and advanced light water reactors (ALWRs) planned for near term construction has evolved over several decades to permit effective regulation of the light water reactor (LWR) designs. To address other reactor types, development of a framework that possesses the attributes of being technology neutral, risk-informed and performance-based is ongoing by several U.S. and international organizations. To support development of a revised framework, the Electric Power Research Institute (EPRI) conducted research to identify and assess specific elements of the proposed possible frameworks; to develop a preliminary integrated framework based on the results of this review and evaluation; and to provide recommendations in areas where additional development and testing would appear to be most beneficial. This research identified Fundamental Safety Principles (FSPs) and Fundamental Design Principles (FDPs) to be the cornerstones that provide the underlying basis for the proposed integrated framework. FSPs provide the safety objectives which are to be achieved. Associated with each FSP is a corresponding FDP that provides mechanisms by which achievement of the FSP can be demonstrated. In this paper we describe the 11 FSPs and associated FDPs that were developed. We note that these FSPs / FDPs are for the most part consistent with comparable criteria provided in the frameworks which were reviewed. The results of this research have been and are being used to support ongoing industry efforts to develop applicable standards and guidance for licensing of advanced plants (Generation 3 Plus and 4) that address safety characteristics which differ from the current generation of plants and advanced LWRs.

Download Full-text

Problems and prospects of new generation light-water reactors at supercritical pressure

Thermal Engineering ◽

10.1134/s0040601508050029 ◽

2008 ◽

Vol 55 (5) ◽

pp. 365-371 ◽

Cited By ~ 1

Author(s):

Yu. M. Semchenkov ◽

A. S. Dukhovenskii ◽

P. N. Alekseev ◽

A. A. Proshkin ◽

V. N. Mukhachev ◽

...

Keyword(s):

Supercritical Pressure ◽

Light Water Reactors ◽

Light Water ◽

Water Reactors ◽

New Generation

Download Full-text

Parameter Estimation for Predictive Simulation of Oscillatory Systems with Model Discrepancy**This research was supported in part by the Air Force Office of Scientific Research grant AFOSR FA9550-11-1-0152. It was also supported by the Consortium for Advanced Simulation of Light Water Reactors (http://www.casl.gov), an Energy Innovation Hub, (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725.

IFAC-PapersOnLine ◽

10.1016/j.ifacol.2016.10.203 ◽

2016 ◽

Vol 49 (18) ◽

pp. 428-433

Author(s):

Jerry A. McMahan ◽

Ralph C. Smith

Keyword(s):

Air Force ◽

Nuclear Reactors ◽

Department Of Energy ◽

Light Water Reactors ◽

Light Water ◽

Oscillatory Systems ◽

Energy Innovation ◽

Model Discrepancy ◽

Water Reactors ◽

Research Grant

Download Full-text

ES-3100: A New Generation Shipping Container for Bulk Highly Enriched Uranium and Other Fissile Materials

Transportation, Storage, and Disposal of Radioactive Materials ◽

10.1115/pvp2004-2777 ◽

2004 ◽

Author(s):

Jeffrey G. Arbital ◽

Gerald A. Byington ◽

Dean R. Tousley

Keyword(s):

Department Of Energy ◽

Department Of Transportation ◽

Regulatory Requirements ◽

Dynamic Impact ◽

Element Analysis ◽

Shipping Container ◽

Nuclear Security ◽

Enriched Uranium ◽

New Generation ◽

The U.S

The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA) is shipping bulk quantities of surplus fissile materials, primarily highly enriched uranium (HEU), over the next 15 to 20 years for disposition purposes. The U.S. Department of Transportation (DOT) specification 6M container is the package of choice for most of these shipments. However, the 6M does not conform to the Type B packaging requirements in the Code of Federal Regulations (10CFR71) and, for that reason, is being phased out for use in the secure transportation system of DOE. BWXT Y-12 is currently developing a package to replace the DOT 6M container for HEU disposition shipping campaigns. The new package is based on state-of-the-art, proven, and patented insulation technologies that have been successfully applied in the design of other packages. The new package, designated the ES-3100, will have a 50% greater capacity for HEU than the 6M and will be easier to use. Engineering analysis on the new package includes detailed dynamic impact finite element analysis (FEA). This analysis gives the ES-3100 a high probability of complying with regulatory requirements.

Download Full-text