Author: United States. Department of EnergyPublisher:
ISBN:
Category : Vanadium
Languages : en
Pages :
Book Description
Technical assessment of vanadium-base alloys for fusion reactor applications
Author: United States. Department of EnergyPublisher:
ISBN:
Category : Vanadium
Languages : en
Pages :
Book Description
Vanadium-base Alloys for Fusion Reactor Applications
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Vanadium-base alloys offer potentially significant advantages over other candidate alloys as a structural material for fusion reactor first wall/blanket applications. Although the data base is more limited than that for the other leading candidate structural materials, viz., austenitic and ferritic steels, vanadium-base alloys exhibit several properties that make them particularly attractive for the fusion reactor environment. This paper presents a review of the structural material requirements, a summary of the materials data base for selected vanadium-base alloys, and a comparison of projected performance characteristics compared to other candidate alloys. Also, critical research and development (R and D) needs are defined.
Technical Assessment of Vanadium-base Alloys for Fusion Reactor Applications. Volume 2. Review of Properties
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Separate abstracts were prepared for each of the 5 included sections. (MOW).
Vanadium Alloys for Structural Applications in Fusion Systems
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 21
Book Description
The current knowledge is reviewed on (1) the effects of neutron irradiation on tensile strength and ductility, ductile-brittle transition temperature, creep, fatigue, and swelling of vanadium-base alloys, (2) the compatibility of vanadium-base alloys with liquid lithium, water, and helium environments, and (3) the effects of hydrogen and helium on the physical and mechanical properties of vanadium alloys that are potential candidates for structural materials applications in fusion systems. Also, physical and mechanical properties issues are identified that have not been adequately investigated in order to qualify a vanadium-base alloy for the structural material in experimental fusion devices and/or in fusion reactors.
Fusion Energy Update
Author: Development of Vanadium Base Alloys for Fusion First-wall
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 41
Book Description
Vanadium alloys have been identified as a leading candidate material for fusion first-wall/blanket applications. Certain vanadium alloys exhibit favorable safety and environmental characteristics, good fabricability, high temperature and heat load capability, good compatibility with liquid metals and resistance to irradiation damage effects. The current focus is on vanadium alloys with (3-5)% Cr and (3-5)% Ti with a V-4Cr-4Ti alloy as the leading candidate. Preliminary results indicate that the crack-growth rates of certain alloys are not highly sensitive to irradiation. Results from the Dynamic Helium Charging Experiment (DHCE) which simulates fusion relevant helium/dpa ratios are similar to results from neutron irradiated material. This paper presents an overview of the recent results on the development of vanadium alloys for fusion first wall/blanket applications.
Selected Properties of Vanadium Alloys for Reactor Application
Author: K. F. SmithPublisher:
ISBN:
Category : Alloys
Languages : en
Pages : 40
Book Description
Results indicate the preliminary feasibility of these alloys from all viewpoints under examination and suggest the desirability of studying fabrication problems of alloys and improved reduction methods for vanadium metal.
Structural Alloys for Nuclear Energy Applications
Author: Robert OdettePublisher: Newnes
ISBN: 012397349X
Category : Technology & Engineering
Languages : en
Pages : 673
Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors’ unique personal insight from decades of frontline research, engineering and management. Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
Effect of Dynamically Charged Helium on Mechanical Properties of Vanadium-base Alloys
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
One property of the vanadium-based alloys that is not well understood for the purpose of application as fusion reactor structural material is the effect of simultaneous generation of helium and neutron damage under conditions relevant to fusion-reactor operation. In the present dynamic helium charging experiment (DHCE), helium was produced uniformly in the specimen at linear rates ranging from (approximately)0.4 to 4.2 appm helium/dpa by the decay of tritium during irradiation to 18-31 dpa at 425-600°C in the Li-filled DHCE capsules in the Fast Flux Test Facility. This paper presents results of postirradiation tests of mechanical properties of V-4Cr-4Ti alloy which has been identified as the most promising candidate alloy on the basis of its superior baseline and irradiation properties. Effects of helium on tensile strength and ductility were insignificant for test temperatures>420°C. However, room-temperature ductilities of the DHCE specimens were higher than those of the non-DHCE specimens (negligible helium generation) whereas strengths were lower, indicating that different types of hardening centers are produced during the DHCE and non-DHCE irradiation. Ductile-brittle transition behavior of the DHCE specimens was also determined from bend tests on TEM disks and broken tensile specimens. No brittle behavior was observed at temperatures>-150°C for DHCE specimens. Predominantly brittle-cleavage fracture morphologies were observed only at -196°C in some specimens that were irradiated to 31 dpa at 425°C during DHCE. In strong contrast to tritium-trick experiments in which a large amount of helium is produced in absence of displacement damage, no intergranular fracture was observed in any tensile or bend-tested specimens that were irradiated in the DHCE.
Author: