Generation IV Nuclear Energy Systems
Technical Documents
The following technical documents were prepared in support of the Gen IV Nuclear Energy Systems Program. The documents are listed under the program work breakdown structure/technical area and are in reverse chronological order. All documents are in PDF format.
- Generation IV Nuclear Energy Systems Ten-Year Program Plan - Fiscal Year 2007
- Generation IV Nuclear Energy Systems Ten-Year Program Plan - Fiscal Year 2007 (Vol. 1) - September 2007 — 1.5MB
- FY 2007 Ten-Year Program Plan - Appendix 1.0 - NGNP - September 2007 — 1.1MB
- FY 2007 Ten-Year Program Plan - Appendix 2.0 - SCWR - September 2007 — 353KB
- FY 2007 Ten-Year Program Plan - Appendix 3.0 - GFR - September 2007 — 247KB
- FY 2007 Ten-Year Program Plan - Appendix 4.0 - LFR - September 2007 — 417KB
- FY 2007 Ten-Year Program Plan - Appendix 5.0 - SFR - September 2007 — 161KB
- FY 2007 Ten-Year Program Plan - Appendix 6.0 - MSR - September 2007 — 268KB
- FY 2007 Ten-Year Program Plan - Appendix 7.0 - D&EM - September 2007 — 56KB
- FY 2007 Ten-Year Program Plan - Appendix 8.0 - Energy Conversion - September 2007 — 86KB
- FY 2007 Ten-Year Program Plan - Appendix 9.0 - Materials - September 2007 — 231KB
- Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs - March 2007 — 30MB
- Generation IV Nuclear Energy Systems Ten-Year Program Plan - Fiscal Year 2006
- Generation IV Nuclear Energy Systems Ten-Year Program Plan - Fiscal Year 2006 (Vol. 1) - July 2006 — 1.1MB
- FY 2006 Ten-Year Program Plan - Appendix 1.0 - NGNP - July 2006 — 734KB
- FY 2006 Ten-Year Program Plan - Appendix 2.0 - SCWR - July 2006 — 278KB
- FY 2006 Ten-Year Program Plan - Appendix 3.0 - GFR - July 2006 — 250KB
- FY 2006 Ten-Year Program Plan - Appendix 4.0 - LFR - July 2006 — 645KB
- FY 2006 Ten-Year Program Plan - Appendix 5.0 - SFR - July 2006 — 160KB
- FY 2006 Ten-Year Program Plan - Appendix 6.0 - MSR - July 2006 — 251KB
- FY 2006 Ten-Year Program Plan - Appendix 7.0 - D&EM - July 2006 — 56KB
- FY 2006 Ten-Year Program Plan - Appendix 8.0 - Energy Conversion - July 2006 — 65KB
- FY 2006 Ten-Year Program Plan - Appendix 9.0 - Materials - July 2006 — 240KB
- Generation IV Nuclear Energy Systems Ten-Year Program Plan - FY-2005 (Vol. 1) - March 2005 — 1.1MB
1.02 Very High Temperature Reactor (VHTR) / Next-Generation Nuclear Plant (NGNP)
1.02 Very High Temperature Reactor (VHTR) / Next-Generation Nuclear Plant (NGNP)
- AGR Fuel Development - Coater and Control System Upgrade - March, 2007 — 15MB
- Additional Physical Property Measurements and Assessment of Salt Compositions Proposed for the Intermediate Heat Transfer Loop - September 30, 2006 — 457KB
- Status of Initial Assessment of Physical and Mechanical Properties of Graphite Grades for NGNP Applications - September 5, 2006 — 3.2MB
- Preliminary Issues Associated with the Next Generation Nuclear Plant Intermediate Heat Exchanger Design - September 2006 — 9.9MB
- Preliminary Materials Selection Issues for the Next Generation Nuclear Plant Reactor Pressure Vessel - September 2006 — 5.3MB
- Summary of Studies of Aging and Environmental Effects on Inconel 617 and Haynes 230 - September 2006 — 3.7MB
- Next Generation Nuclear Plant Methods Technical Program Plan - September 2006 — 4.7MB
- Next Generation Nuclear Plant Materials Research and Development Program Plan - August 2006 — 4.1MB
- Conceptual Design for a High-temperature Gas Loop Test Facility - August 2006 — 6.6MB
- Kinetics of Gas Reactions and Environmental Degradation in NGNP Helium - June 2006 — 813KB
- Refueling Options and Considerations for Liquid-Salt-Cooled Very High-Temperature Reactors - June 2006 — 5.4MB
- Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop - June 2006 — 719KB
- Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - March 2006 — 8.2MB
- Trade Studies for the Liquid-Salt-Cooled Very High-Temperature Reactor: Fiscal Year 2006 Progress Report - February 2006 — 6.3MB
- Evaluation of the Initial Critical Configuration of the HTR-10 Pebble-Bed Reactor - September 28, 2005 — 1.3MB
- Development of an Experiment for Measuring Flow Phenomena Occurring in a Lower Plenum for VHTR CFD Assessment - September 21, 2005 — 12MB
- Chemical Considerations for the Selection of the Coolant for the Advanced High-Temperature Reactor - September 14, 2005 — 379KB
- FY2005 Ten-Year Program Plan - Appendix 1.0 - NGNP - March 2005 — 1.0MB
- Scaling Studies and Conceptual Experiment Designs for NGNP CFD Assessment - November 30, 2004 — 6.6MB
- Next Generation Nuclear Plant- Design Methods Development and Validation Research and Development Program Plan - September 2004 — 1.8MB
- Reactor Physics Parametric and Depletion Studies in Support of TRISO Particle Fuel Specification for the Next Generation Nuclear Plant - September 2004 — 1.6MB
- Effective Use of Zirconium Carbide Coatings on the VHTR Core Nuclear Design, - December 2003
- Design Features and Technology Uncertainties for the Next Generation Nuclear Plant - Independent Technology Review Group - June 30, 2004 — 882KB
- University Centered Base Technology Program - White Paper - May 10, 2007 — 135KB
- Supercritical Water Radiolysis Chemistry - Supercritical Water Corrosion - September 2006 — 2.9MB
- Stress Corrosion Cracking of Candidate Alloys for the Supercritical Water Reactor Concept - September 2006 — 4.4MB
- Developing and Evaluating Candidate Materials for Generation IV Supercritical Water Reactors - March 2006 — 16MB
- Design Description for INL Supercritical Water Heat Transfer Test Section for Inclusion into the Benson Loop - October 2005 — 1.5MB
- Initial Implementation of Multi-Channel Thermal-Hydraulics Capability in Frequency Domain SCWR Stability Analysis Code SCWRSA - September 15, 2005 — 690KB
- Stress Corrosion Cracking of Candidate Alloys for the Supercritical Water Reactor Concept - September 2005 — 2.4MB
- FY2005 Ten-Year Program Plan - Appendix 2.0 - SCWR - March 2005 — 271KB
- Proton Irradiation Study of GFR Candidate Ceramics - October 24, 2006 — 3.5MB
- Gas-Cooled Fast Reactor Guard Containment Design - 2006 Final Report - September 2006 — 2.1MB
- Grain Boundary Engineering and Radiation Resistance of GFR Candidate Metallic Materials - July 31, 2006 — 5.3MB
- Transient Liquid Phase Bonding of Ferritic Oxide Dispersion Strengthened Alloys - June 26, 2006 — 695KB
- Pin Core Subassenbly Design - April 2006 — 1.3MB
- Gas-Cooled Fast Reactor (GFR) FY05 Annual Report - September 30, 2005 — 37MB
- Ion Irradiation Study on Microstructure Stability of GFR Ceramics: ZrC, ZrN, TiC, TiN and SiC Irradiated with 1 MeV Kr Ions to 10 and 70 dpa at 800°C - September 27, 2005 — 23MB
- Gas-Cooled Fast Reactor (GFR) Decay Heat Removal Concepts - September 15, 2005 — 23MB
- Modeling of GFR Decay Heat Removal in a Depressurization Accident - August 31, 2005 — 2.5MB
- Materials Fabricated for FUTURIX-MI Experiments - May 1, 2005 — 6.0MB
- Analysis Of Depressurization Accident For A 2400 MW Gas Cooled Reactor - Effects Of The Reactor Cavity Cooling System - April 15, 2005 — 4.1MB
- FY2005 Ten-Year Program Plan - Appendix 3.0 - GFR - March 2005 — 252KB
- Interim Status Report on the Design of the Gas-Cooled Fast Reactor (GFR) - January 31, 2005 — 1.0MB
- Passive Decay Heat Removal For A 2400 Mw Pin Core By Natural Circulation - January 2005 — 19MB
- Gas-Cooled Fast Reactor (GFR) FY04 Annual Report - September 30, 2004 — 5.3MB
- Report on the Feasibility of GFR Fuel for minor Actinide Management - August 30, 2004 — 2.5MB
- Initial Requirements for GFR System Design, Performance, and Safety Analysis Model - August 27, 2004 — 853KB
- The Gas Fast Reactor (GFR) Survey of Materials Experience and R&D Needs to Assess Viability - April 30, 2004 — 1.6MB
- Status Report on the Small Secure Transportable Autonomous Reactor (SSTAR)/Lead-Cooled Fast Reactor (LFR) and Supporting Research and Development - September 29, 2006 — 7.7MB
- Model-Based Analysis of Corrosion Test Results and Extraction of Long-Term Corrosion Rates - September 22, 2006 — 95KB
- Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule - September 2006 — 2.5MB
- Options for an Early LFR Technology Demonstrator - High-Confidence Design Options for Lead-Cooled Fast Reactors - March 30, 2006 — 414KB
- FY2005 Ten-Year Program Plan - Appendix 4.0 - LFR - March 2005 — 247KB
- FY2005 Ten-Year Program Plan - Appendix 5.0 - SFR - March 2005 — 137KB
- Thermal- and Fast-Spectrum Molten Salt Reactors for Actinide Burning and Fuel Production - August 13, 2007 — 305KB
- FY2005 Ten-Year Program Plan - Appendix 6.0 - MSR - March 2005 — 571KB
- Prioritization of VHTR System Modeling Needs Based on Phenomena Identification, Ranking and Sensitivity Studies - April, 2006 — 5.4MB
- Annual Report of the International Nuclear Energy Research Initiative OSMOSE Project (FY06) - September 30, 2006 — 669KB
- Results of Calculations for the OSMOSE Samples in the MINERVE Reactor R1-UO2, R2-UO2 and R1-MOX Configurations - September, 2006 — 1.1MB
- OSMOSE Program: Statistical Review of Oscillation Measurements in the MINERVE Reactor R1-UO2 Configuration - September, 2006 — 867KB
- Enhancement of REBUS-3/DIF3D for Whole-Core Neutronic Analysis of Prismatic Very High Temperature Reactor (VHTR) - September 30, 2006 — 754KB
- Cost Estimating Guidelines for Generation IV Nuclear Energy Systems - 2006 - September 29, 2006 — 881KB
- Coupling RELAP5-3D and FLUENT to Analyze a Very High Temperature Reactor (VHTR) Outlet Plenum - August 2006 — 771KB
- Cost Estimating Guidelines for Generation IV Nuclear Energy Systems - 2005 - September 30, 2005 — 539KB
- Annual Report of the International Nuclear Energy Research Initiative OSMOSE Project (FY05) - September 30, 2005 — 583KB
- Evaluation of High Temperature Gas-Cooled Reactor Physics Experiments as VHTR Benchmark Problems - September 15, 2005 — 2.9MB
- Impact of Spectral Transition Zone in Reference ENIGMA Configuration - August 31, 2005 — 272KB
- FY2005 Ten-Year Program Plan - Appendix 7.0 - D&EM - March 2005 — 48KB
- Preliminary Assessment of Existing Experimental Data for Validation of Reactor Physics and Data for NGNP Design and Analysis - September 15, 2004 — 235KB
- Initial VHTR Accident Scenario Classification: Models and Data - September 2004 — 399KB
- Specification for an Integrated Nuclear Energy Economics Model - September 2004 — 85KB
- A Generic EXCEL-based Model for Computation of the Projected Levelized Unit Electricity Cost (LUEC) from Generation IV Reactor Systems September 2004 — 122KB
- Gen IV Materials Handbook Beta Release for Structural and Functional Evaluation - September 12, 2006 — 566KB
- 2400 MWt Gas-Cooled Fast Reactor DHR Studies Status Update - August 31, 2006 — 380KB
- Combined Active/Passive Decay Heat Removal Approach for the 2400 MWt Gas-Cooled Fast Reactor - March 31, 2006 — 905KB
- Updated Generation IV Reactors Integrated Materials Technology Program Plan Revision 2 - December 31, 2005 — 10MB
- Gen IV Materials Handbook Implementation Plan - March 2005 — 152KB
- FY2005 Ten-Year Program Plan - Appendix 9.0 - Materials - March 29, 2005 — 222KB
- Updated Generation IV Reactors Integrated Materials Technology Program Plan, Revision 2 - December 31, 2005 — 10MB
- Applicability of Supercritical CO2 Power Conversion Systems to GEN IV Reactors - September 15, 2006 — 7.4MB
- Control System Strategies and Dynamic Response for Supercritical CO2 Power Conversion Cycles - September 15, 2006 — 1.6MB
- Effects of Materials Testing Requirements and Planning for Implementation of Initial Test Program for Liquid Salt Intermediate Loops - September 2006 — 162KB
- Energy Conversion Advanced Heat Transport Loop and Power Cycle - August 2006 — 1.0MB
- Concept Design for a High Temperature Helium Brayton Cycle with Interstage Heating and Cooling - July 1, 2006 — 1.1MB
- Analysis of Radial Compressor Options for Supercritical CO2 Power Conversion Cycles - June 30, 2006 — 929KB
- Small Scale Closed Brayton Cycle Dynamic Response Experiment Results - June 1, 2006 — 5.2MB
- FY2005 Ten-Year Program Plan - Appendix 8.0 - Energy Conversion - March 2005 — 62KB
- Supercritical CO2 Plant Cost Assessment - September 2004 — 910KB
- 300 Mwe Supercritical CO2 Plant Layout and Design - June 2004 — 1.6MB
- The U.S. Generation IV Fast Reactor Strategy - December 2006 — 803KB
- Prototype Application of Gen IV Technical Maturity Assessment Methodology - June 2006 — 159KB
- Advanced Corrosion-Resistant Zirconium Alloys for High Burnup and Generation IV Applications - 2003-2007
- Executive Summary — 28KB
- Task 1: Alloy Fabrication and Characterization — 128KB
- Task 2: Corrosion Testing at 360°C — 359KB
- Task 3: Corrosion Testing at 500°C — 226KB
- Task 4: Oxide Characterization — 2.4MB
- Task 5: Discussion and Modeling — 138KB
- Appendix A: Water 360°C Experiments — 433KB
- Appendix B: 500°C Steam - Wesinghouse — 245KB
- Appendix C: SCW - Static Autoclave - KAERI — 156KB
- Appendix D: Alloys and Samples Examined in Cross-Section with the Microbeam — 3.2MB
- Appendix E: Pole Figures from Model Alloy Oxides in Frontal Geometry — 7.3MB
- Appendix F: Characterization of As-Fabricated Model Alloys — 630KB
- Design Strategies and Evaluation for Sharing Systems at Multi-Unit Plants - Phase I - August 2007 — 1.9MB
- Computer Models for IRIS Control System Transient Analysis - January 2007 — 694KB
- Signal Processing Algorithm Implementation for In Vessel Level Measurement - September 2006 — 3.0MB
- Development of Advanced Instrumentation and Control for an Integrated Primary System Reactor - December 15, 2005 — 3.7MB
- Passive Safety Optimization in Liquid Sodium-Cooled Reactors - December 2005 — 1.8MB
- Passive Safety Optimization in Liquid Sodium-Cooled Reactors - December 2005 — 1.8MB