Published 2007 | Version v1
Report

Design issues and implications for structural integrity of fusion power plant components

  • 1. EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon (United Kingdom)

Description

Full text: The criteria and implications for successful design, licensing and power plant operation are assessed, and imposed constraints and limitations are examined. The design of a reliable fusion power plant is dependent on the availability of licensed nuclear materials and the structural-thermal loading conditions during normal and abnormal (disruptions) events. The various conditions in a tokamak lead to structural damage and possible failure. Taking into consideration all the possible structural failure mechanisms, the most likely are combinations of fatigue and creep. Issues encountered in the fusion environment are the significant amount of irradiation creep, the large ratio of helium production to displacement damage, and the degradation of fatigue strength and ductility, effects which are even encountered at low temperatures. Component design, and accurate prediction of lifetime, requires established material databases and design curves, specification for fabrication and testing, inspection methods, and rules and constraints for design, and in-service conditions. The issues involved are classification of components according to their functionality, physical position in the machine and safety importance, classification of loading conditions, and choice of elastic or inelastic analysis. The existing design codes guard against creep and fatigue but do not directly address neutron irradiation. The issues associated with irradiation creep-fatigue, since they impact the design and licensing processes of future fusion power plants, are presented and discussed. The codes distinguish between failure criteria under steady and cyclic loads, and lay down rules for failure prediction under combined creep-fatigue conditions. Currently, there are no established fusion specific licensing processes or component design codes. Any limits imposed on designs or performance, are taken from existing design codes developed by the fission industry. There is a need to initiate the process of defining and developing tools for the design and licensing of fusion components and facilities to ensure nuclear safety. (author)

Part of:
2. IAEA technical meeting on first generation of fusion power plants: Design and technology. Book of abstracts and programme

Additional details

Publishing Information

Imprint Title
2. IAEA technical meeting on first generation of fusion power plants: Design and technology. Book of abstracts and programme
Imprint Pagination
45 p.
Journal Page Range
p. 21
Report number
INIS-XA--981

Conference

Title
Design and technology
Acronym
2. IAEA technical meeting on first generation of fusion power plants
Dates
20-22 Jun 2007
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
42024731
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CREEP; DAMAGE; DESIGN; DUCTILITY; DYNAMIC LOADS; FAILURES; FATIGUE; HELIUM; IRRADIATION; LICENSING; NEUTRONS; SAFETY; TESTING; THERMONUCLEAR POWER PLANTS; TOKAMAK DEVICES
Descriptors DEC
BARYONS; CLOSED PLASMA DEVICES; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; FLUIDS; GASES; HADRONS; MECHANICAL PROPERTIES; NONMETALS; NUCLEONS; POWER PLANTS; RARE GASES; TENSILE PROPERTIES; THERMAL POWER PLANTS; THERMONUCLEAR DEVICES

Optional Information

Notes
This record replaces 38090942
Secondary number(s)
MCP.O--10