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pro vyhledávání: '"W.G. Steele"'
Autor:
W.G. Steele, H.W. Coleman
Publikováno v:
Mathematics for Mechanical Engineers ISBN: 9781003067672
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e9df8be2477a2caefd698bb4cf61fc9a
https://doi.org/10.1201/9781003067672-13
https://doi.org/10.1201/9781003067672-13
Publikováno v:
1998 Annual Conference Proceedings.
Publikováno v:
1996 Annual Conference Proceedings.
Publikováno v:
International Journal of Solids and Structures. 47:186-203
In this paper, we illustrate a formal calibration, validation, and verification process that includes uncertainty in an internal state variable plasticity-damage model that is implemented in a finite element code. The physically motivated continuum m
Autor:
W.G. Steele
The Mississippi DOE EPSCoR planning grant committee identified three focus areas for a proposal submitted on January 25, 1995, to the US DOE: Human Resource Development, Environmental Synergisms from Fuel Mixtures of Tire Particles and Low Rank Coals
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8f9adb6cc97fbb489cdd58e4398f31c8
https://doi.org/10.2172/10187175
https://doi.org/10.2172/10187175
Publikováno v:
International Journal of Design Engineering. 2:47
In this paper, we present a methodology for simulation-based product design optimisation using an internal state variable (ISV) constitutive modelling approach that captures the microstructure-property relations in the material. By modelling the stoc
Publikováno v:
Nuclear Engineering and Design. 70:187-199
A computer code is developed to model fission gas disposition in UO2 fuel during nearly isothermal heating, as would result from decay heat. The intragranular analysis, random diffusion model, uses a spatial solution for random migration and bubble c
Publikováno v:
Nuclear Engineering and Design. 113:289-295
An analysis of fission gas release and induced swelling in steady state irradiated U—Pu—Zr metal fuels is developed and computer coded. The code is used to simulate, with fair success, some gas release and induced swelling data obtained under the
Autor:
C.P.C. Wong, K.R. Schultz, J.K. Garner, I. Maya, S.J. Bradbury, D.H. Berwald, C.G. Hoot, W.G. Steele
The safety features of the reference fission suppressed fusion breeder reactor are presented. These include redundancy and overcapacity in primary coolant system components to minimize failure probability, an improved valve location logic to provide
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1662d3db7dd5fc707e444a7cb16f8285
https://doi.org/10.2172/6437275
https://doi.org/10.2172/6437275
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