Published 1982
| Version v1
Journal article
Thermoviscoplastic analysis of first walls subjected to fusion power transients
Creators
- 1. Department of Mechanical Engineering, University of New Mexico, Albuquerque, New Mexico
Description
Abrupt thermal fluxes on the first walls of fusion reactors represent a loading environment that requires advanced analytical capabilities. Solutions are needed to a wide range of postulated conditions to provide guidance for safety features and design modifications. A brief outline is given of a computer code that provides an integrated procedure for handling thermal stresses and large deformations under dynamic conditions. The code includes a new thermoviscoplastic constitutive equation that incorporates thermal softening, failure and strain rate. Solutions to several verification and illustrative problems are given
Additional details
Publishing Information
- Journal Title
- Am. Soc. Mech. Eng., [Pap.]
- Journal Issue
- 82-pvp-66
- Series
- Am. Soc. Mech. Eng., [Pap.].
- ISSN
- 0402-1215
Conference
- Title
- ASME pressure vessel and piping conference.
- Dates
- 27 Jun - 1 Jul 1982.
- Place
- Orlando, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15023347
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ANALYTICAL SOLUTION; COMPUTER CODES; COMPUTER-AIDED DESIGN; DEFORMATION; FAILURES; FIRST WALL; HEAT FLUX; NUMERICAL DATA; PLASTICITY; REACTOR SAFETY; STRAINS; STRESS ANALYSIS; THERMAL ANALYSIS; THERMAL STRESSES; THERMONUCLEAR REACTORS; TRANSIENTS; VISCOSITY
- Descriptors DEC
- DATA; INFORMATION; MECHANICAL PROPERTIES; SAFETY; STRESSES; THERMONUCLEAR REACTOR WALLS
Optional Information
- Secondary number(s)
- CONF-820601--.