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Design of Radiation-Tolerant Alloys for Generation IV
Sponsor:
U.S. Department of Energy, Nuclear Energy Research Initiative (NERI)
Under the Generation IV Reactor initiative, revolutionary improvements in nuclear energy system design in the areas of sustainability, economics, and safety and reliability are being pursued. To meet these goals, advanced nuclear energy systems demand materials that minimize resource use, minimize waste impact, improve proliferation |
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Developing and Evaluating Candidate Materials for Generation IV
Sponsor:
U.S. Department of Energy, Nuclear Energy Research Initiative (I-NERI)
The goal of this project is to establish candidate materials for supercritical water reactor designs and to initiate the evaluation of the mechanical properties, dimensional stability, and corrosion resistance. To overcome the principal technical and scientific obstacles to the long-term future use of nuclear energy, |
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Stress Corrosion Cracking and Corrosion of Candidate Alloys for the Supercritical Water Reactor Concept
Sponsor:
DOE-NERI program
Supercritical water presents unique challenges to the long-term operation of engineering materials. The generation of oxygen and hydrogen gas by radiolysis and the high solubility of these gases in supercritical water may result in higher corrosion and stress corrosion cracking rates than experienced with other |
BWRVIP Highly Irradiated Stainless Steel Crack Growth
Sponsor:
General Electric
This program focuses on post-test fracture surface examination of CGR samples in a scanning electron microscope, SEM, in a hot cell, in support of a larger program being conducted by General Electric for the Electric Power Research Institute. The microscope we will be using is |
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Localized Deformation as a Primary Cause of Irradiation Assisted Stress Corrosion Cracking
Sponsor:
U. S. Department of Energy, Nuclear Engineering Education Research Program
The purpose of this project is to establish that localized deformation in irradiated LWR core internals is a primary factor in irradiation assisted stress corrosion cracking (IASCC). This mode of degradation is a continuing problem in existing LWRs and is expected to be a more |
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Candidate Materials Evaluation for the Supercritical Water-cooled Reactor
Sponsor:
U. S. Department of Energy, Nuclear Energy Research Initiative (NERI)
The supercritical-water-cooled reactor (SCWR) system is being evaluated as a Generation IV concept because it and builds on currently proven light water technology to provide for high thermal efficiency and plant simplification. Development, testing, and selection of suitable materials for cladding and internal components are |
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Alloys for 1000C Service in the Next Generation Nuclear Plant
Sponsor:
U.S. Department of Energy, Nuclear Energy Research Initiative (NERI)
The objective of the proposed research is to define strategies for the improvement of alloys for structural components, such as the intermediate heat exchanger and primary-to-secondary piping, for service at 1000C in the He environment of the NGNP. Specifically, we will investigate the oxidation/carburization behavior |
Accelerator-Based Irradiation Creep of Pyrolicitc Carbon Used in TRISO Fuel Particles for the VHTR
Sponsor:
DOE-NERI
Pyrolytic carbon (PyC) is used as one of the structural materials for the TRISO fuel particles in the next generation of gas cooled Very-High-Temperature Reactors (VHTR). Creep of pyrocarbon layers in the TRISO particles under irradiation can be significantly anisotropic via carbon atom displacements despite |
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