h"p://fire.pppl.gov 1 MagneBc Fusion Program Leaders (MFPL) Road Map Study Goal: ... more h"p://fire.pppl.gov 1 MagneBc Fusion Program Leaders (MFPL) Road Map Study Goal: Develop and assess three aggressive technically feasible paths for the US Fusion Program moAvate a commitment to DEMO on the Amescale of ITER Q ≈ 10 experiments (nominally 2028) with DEMO by mid-‐century. 1) ITER directly to a Tokamak DEMO (possibly staged) 2) ITER plus Fusion Nuclear Science Facility leading to a Tokamak DEMO 3) ITER plus addiAonal faciliAes leading to a QS - ‐ Stellarator DEMO Each of these paths will include major aspects of a broad supporAng research program. Working Group Members:
Materials research for fusion reactors is overviewed from Japanese, EU and US perspectives. Empha... more Materials research for fusion reactors is overviewed from Japanese, EU and US perspectives. Emphasis is placed on programs and strategies for developing blanket structural materials, and recent highlights in research and development for reduced activation ferritic martensitic steels, vanadium alloys and SiC/SiC composites, and in mechanistic experimental and modeling studies. The common critical issue for the candidate materials is the
We present an overview of key aspects for development of steels for fission and fusion energy app... more We present an overview of key aspects for development of steels for fission and fusion energy applications, by linking material fabrication to thermo-mechanical properties through a physical understanding of microstructure evolution. Numerous design constraints (e.g. reduced activation, low ductile-brittle transition temperature, low neutron-induced swelling, good creep resistance, and weldability) need to be considered, which in turn can be controlled through material composition and processing techniques. Recent progress in the development of high-performance steels for fossil and fusion energy systems is summarized, along with progress in multiscale modeling of mechanical behavior in metals. Prospects for future design of optimum structural steels in nuclear applications by utilization of the hierarchy of multiscale experimental and computational strategies are briefly described.
Atomic collision processes are fundamental to numerous advanced materials technologies such as el... more Atomic collision processes are fundamental to numerous advanced materials technologies such as electron microscopy, semiconductor processing and nuclear power generation. Extensive experimental and computer simulation studies over the past several decades provide the physical basis for understanding the atomic-scale processes occurring during primary displacement events. The current international standard for quantifying this energetic particle damage, the Norgett-Robinson-Torrens displacements per atom (NRT-dpa) model, has nowadays several well-known limitations. In particular, the number of radiation defects produced in energetic cascades in metals is only ~1/3 the NRT-dpa prediction, while the number of atoms involved in atomic mixing is about a factor of 30 larger than the dpa value. Here we propose two new complementary displacement production estimators (athermal recombination corrected dpa, arc-dpa) and atomic mixing (replacements per atom, rpa) functions that extend the NRT-...
Well-coordinated international fusion materials research on multiple fundamental feasibility issu... more Well-coordinated international fusion materials research on multiple fundamental feasibility issues can serve an important role during the next ten years. Due to differences in national timelines and fusion device concepts, a parallel-track (multimodal) approach is currently being used for developing fusion energy. An overview is given of the current state-of-the-art of major candidate materials systems for next-step fusion reactors, including a summary of existing knowledge regarding operating temperature and neutron irradiation fluence limits due to hightemperature strength and radiation damage considerations, coolant compatibility information, and current industrial manufacturing capabilities. There are two interrelated overarching objectives of fusion materials research to be performed in the next decade: (1) understanding materials science phenomena in the demanding DT fusion energy environment, and (2) application of this knowledge to develop and qualify materials to provide the basis for next-step facility construction authorization by funding agencies and public safety licensing authorities. The critical issues and prospects for development of high-performance fusion materials are discussed along with recent research results and planned activities of the international materials research community.
We present an overview of key aspects for development of steels for fission and fusion energy app... more We present an overview of key aspects for development of steels for fission and fusion energy applications, by linking material fabrication to thermo-mechanical properties through a physical understanding of microstructure evolution. Numerous design constraints (e.g. reduced activation, low ductile-brittle transition temperature, low neutron-induced swelling, good creep resistance, and weldability) need to be considered, which in turn can be controlled through material composition and processing techniques. Recent progress in the development of high-performance steels for fossil and fusion energy systems is summarized, along with progress in multiscale modeling of mechanical behavior in metals. Prospects for future design of optimum structural steels in nuclear applications by utilization of the hierarchy of multiscale experimental and computational strategies are briefly described.
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)
The proposal is to make large deuterium (D-D) magnetic fusion power plants in which some (most) o... more The proposal is to make large deuterium (D-D) magnetic fusion power plants in which some (most) of the tritium produced by fusion is removed and stored. This tritium will ultimately decay to helium-3 that will be recycled to supplement the helium-3 produced by fusion. Thus the dominant fusion becomes that of deuterium and helium-3. The tritium would be removed using ion cyclotron waves in a similar manner to that proposed by Chang et al, and tested on TEXTOR, for removing alpha particles from a D-T plasma. Interestingly, with this scheme it only takes about 25 years before the rate of helium-3 production is sufficient to support a doubling of such plants every decade, with very low tritium content. The importance of this is that the production of 14.1 MeV neutrons is substantially reduced over a standard catalyzed D-D plant and even more so over a D-T plant. To be specific, if 90% of the tritium can be removed, the first power plant will average only 5.8% 14.1 MeV neutron power, when averaged over 30 years of operation. (5.8% of total plasma fusion power, any blanket neutron gain is extra). Later generations will get down to less than 4% of 14.1 MeV neutrons by using surplus helium-3 from earlier power plant operation. Ultimately, in steady state, the 14.1 MeV fraction will be 3% of total plasma fusion power. Large tokamak power plants are used to illustrate the approach, because it is possible to use "ITER rules" to develop a consistent system. In reality, at large scale-5000 to 6000 MW thermal-other systems may turn out to be superior.
The International Fusion Materials Irradiation Facility (IFMIF) employs an accelerator based D-Li... more The International Fusion Materials Irradiation Facility (IFMIF) employs an accelerator based D-Li intense neutron source as defined in the 1995-96 Conceptual Design Activity (CDA) study. In 1999, IEA mandated a review of the CDA IFMIF design for cost reduction without change to its original mission. This objective was accomplished by eliminating the previously assumed possibility of potential upgrade of IFMIF beyond the user requirements. The total estimated cost was reduced from $797.2 M to $487.8 M. An option of deployment in 3 stages was also examined to reduce the initial investment and annual expenditures during construction. In this scenario, full performance is achieved gradually with each interim stage as follows. 1st Stage: 20% operation for material selection for ITER breeding blanket, 2nd Stage: 50% operation to demonstrate materials performance of a reference alloy for DEMO, 3rd Stage: full performance operation (2 MW/m2 @ 500 cm3) to obtain engineering data for potentia...
Abstract Materials for future nuclear energy systems must operate under more extreme conditions t... more Abstract Materials for future nuclear energy systems must operate under more extreme conditions than those in current Gen II or Gen III systems. These conditions include higher temperature, higher dpa, and more corrosive environments. This paper reviews some of the fuels and structural materials used in advanced nuclear energy systems and identifies promising candidates for these systems. Fuel systems includes metallic fuels for the sodium cooled reactor, TRISO-coated particle fuel for the high temperature gas reactor, molten salt reactor fuels, and accident tolerant fuels for light water reactors. Structural materials applications include the sodium fast reactor, lead fast reactor, high temperature gas reactor, molten salt reactor and extended life light water reactors. A final section focuses on plasma-facing and blanket materials for deuterium-tritium fusion reactors.
h"p://fire.pppl.gov 1 MagneBc Fusion Program Leaders (MFPL) Road Map Study Goal: ... more h"p://fire.pppl.gov 1 MagneBc Fusion Program Leaders (MFPL) Road Map Study Goal: Develop and assess three aggressive technically feasible paths for the US Fusion Program moAvate a commitment to DEMO on the Amescale of ITER Q ≈ 10 experiments (nominally 2028) with DEMO by mid-‐century. 1) ITER directly to a Tokamak DEMO (possibly staged) 2) ITER plus Fusion Nuclear Science Facility leading to a Tokamak DEMO 3) ITER plus addiAonal faciliAes leading to a QS - ‐ Stellarator DEMO Each of these paths will include major aspects of a broad supporAng research program. Working Group Members:
Materials research for fusion reactors is overviewed from Japanese, EU and US perspectives. Empha... more Materials research for fusion reactors is overviewed from Japanese, EU and US perspectives. Emphasis is placed on programs and strategies for developing blanket structural materials, and recent highlights in research and development for reduced activation ferritic martensitic steels, vanadium alloys and SiC/SiC composites, and in mechanistic experimental and modeling studies. The common critical issue for the candidate materials is the
We present an overview of key aspects for development of steels for fission and fusion energy app... more We present an overview of key aspects for development of steels for fission and fusion energy applications, by linking material fabrication to thermo-mechanical properties through a physical understanding of microstructure evolution. Numerous design constraints (e.g. reduced activation, low ductile-brittle transition temperature, low neutron-induced swelling, good creep resistance, and weldability) need to be considered, which in turn can be controlled through material composition and processing techniques. Recent progress in the development of high-performance steels for fossil and fusion energy systems is summarized, along with progress in multiscale modeling of mechanical behavior in metals. Prospects for future design of optimum structural steels in nuclear applications by utilization of the hierarchy of multiscale experimental and computational strategies are briefly described.
Atomic collision processes are fundamental to numerous advanced materials technologies such as el... more Atomic collision processes are fundamental to numerous advanced materials technologies such as electron microscopy, semiconductor processing and nuclear power generation. Extensive experimental and computer simulation studies over the past several decades provide the physical basis for understanding the atomic-scale processes occurring during primary displacement events. The current international standard for quantifying this energetic particle damage, the Norgett-Robinson-Torrens displacements per atom (NRT-dpa) model, has nowadays several well-known limitations. In particular, the number of radiation defects produced in energetic cascades in metals is only ~1/3 the NRT-dpa prediction, while the number of atoms involved in atomic mixing is about a factor of 30 larger than the dpa value. Here we propose two new complementary displacement production estimators (athermal recombination corrected dpa, arc-dpa) and atomic mixing (replacements per atom, rpa) functions that extend the NRT-...
Well-coordinated international fusion materials research on multiple fundamental feasibility issu... more Well-coordinated international fusion materials research on multiple fundamental feasibility issues can serve an important role during the next ten years. Due to differences in national timelines and fusion device concepts, a parallel-track (multimodal) approach is currently being used for developing fusion energy. An overview is given of the current state-of-the-art of major candidate materials systems for next-step fusion reactors, including a summary of existing knowledge regarding operating temperature and neutron irradiation fluence limits due to hightemperature strength and radiation damage considerations, coolant compatibility information, and current industrial manufacturing capabilities. There are two interrelated overarching objectives of fusion materials research to be performed in the next decade: (1) understanding materials science phenomena in the demanding DT fusion energy environment, and (2) application of this knowledge to develop and qualify materials to provide the basis for next-step facility construction authorization by funding agencies and public safety licensing authorities. The critical issues and prospects for development of high-performance fusion materials are discussed along with recent research results and planned activities of the international materials research community.
We present an overview of key aspects for development of steels for fission and fusion energy app... more We present an overview of key aspects for development of steels for fission and fusion energy applications, by linking material fabrication to thermo-mechanical properties through a physical understanding of microstructure evolution. Numerous design constraints (e.g. reduced activation, low ductile-brittle transition temperature, low neutron-induced swelling, good creep resistance, and weldability) need to be considered, which in turn can be controlled through material composition and processing techniques. Recent progress in the development of high-performance steels for fossil and fusion energy systems is summarized, along with progress in multiscale modeling of mechanical behavior in metals. Prospects for future design of optimum structural steels in nuclear applications by utilization of the hierarchy of multiscale experimental and computational strategies are briefly described.
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)
The proposal is to make large deuterium (D-D) magnetic fusion power plants in which some (most) o... more The proposal is to make large deuterium (D-D) magnetic fusion power plants in which some (most) of the tritium produced by fusion is removed and stored. This tritium will ultimately decay to helium-3 that will be recycled to supplement the helium-3 produced by fusion. Thus the dominant fusion becomes that of deuterium and helium-3. The tritium would be removed using ion cyclotron waves in a similar manner to that proposed by Chang et al, and tested on TEXTOR, for removing alpha particles from a D-T plasma. Interestingly, with this scheme it only takes about 25 years before the rate of helium-3 production is sufficient to support a doubling of such plants every decade, with very low tritium content. The importance of this is that the production of 14.1 MeV neutrons is substantially reduced over a standard catalyzed D-D plant and even more so over a D-T plant. To be specific, if 90% of the tritium can be removed, the first power plant will average only 5.8% 14.1 MeV neutron power, when averaged over 30 years of operation. (5.8% of total plasma fusion power, any blanket neutron gain is extra). Later generations will get down to less than 4% of 14.1 MeV neutrons by using surplus helium-3 from earlier power plant operation. Ultimately, in steady state, the 14.1 MeV fraction will be 3% of total plasma fusion power. Large tokamak power plants are used to illustrate the approach, because it is possible to use "ITER rules" to develop a consistent system. In reality, at large scale-5000 to 6000 MW thermal-other systems may turn out to be superior.
The International Fusion Materials Irradiation Facility (IFMIF) employs an accelerator based D-Li... more The International Fusion Materials Irradiation Facility (IFMIF) employs an accelerator based D-Li intense neutron source as defined in the 1995-96 Conceptual Design Activity (CDA) study. In 1999, IEA mandated a review of the CDA IFMIF design for cost reduction without change to its original mission. This objective was accomplished by eliminating the previously assumed possibility of potential upgrade of IFMIF beyond the user requirements. The total estimated cost was reduced from $797.2 M to $487.8 M. An option of deployment in 3 stages was also examined to reduce the initial investment and annual expenditures during construction. In this scenario, full performance is achieved gradually with each interim stage as follows. 1st Stage: 20% operation for material selection for ITER breeding blanket, 2nd Stage: 50% operation to demonstrate materials performance of a reference alloy for DEMO, 3rd Stage: full performance operation (2 MW/m2 @ 500 cm3) to obtain engineering data for potentia...
Abstract Materials for future nuclear energy systems must operate under more extreme conditions t... more Abstract Materials for future nuclear energy systems must operate under more extreme conditions than those in current Gen II or Gen III systems. These conditions include higher temperature, higher dpa, and more corrosive environments. This paper reviews some of the fuels and structural materials used in advanced nuclear energy systems and identifies promising candidates for these systems. Fuel systems includes metallic fuels for the sodium cooled reactor, TRISO-coated particle fuel for the high temperature gas reactor, molten salt reactor fuels, and accident tolerant fuels for light water reactors. Structural materials applications include the sodium fast reactor, lead fast reactor, high temperature gas reactor, molten salt reactor and extended life light water reactors. A final section focuses on plasma-facing and blanket materials for deuterium-tritium fusion reactors.
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