A Computer Code to Calculate Non-Linear Stresses in a Fusion Reactor

Autor:	M.C. Perrin, D.E. Ruester, B.A. Cramer
Rok vydání:	1985
Předmět:	Source code Materials science media_common.quotation_subject General Engineering Mechanics Fusion power Fluence Physics::Geophysics Stress (mechanics) Nonlinear system Creep Neutron flux Neutron media_common
Zdroj:	Fusion Technology. 8:592-595
ISSN:	0748-1896
Popis:	A non-linear, inelastic stress analysis code, developed at the McDonnel Douglas Astronautics Company (MDAC), was modified to incorporate irradiation effects in the analysis of stress histories within fusion reactor structural components. This code calculates stresses and strains due to temperature gradients, thermal creep, irradiation creep, and differential swelling as a function of neutron wall load and fluence.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::6a7ce28ec13eba9100cfa1f20255867a https://doi.org/10.13182/fst85-a40103 Zobrazit plný text záznamu