Zobrazeno 1 - 10
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pro vyhledávání: '"P.G. Kroeger"'
For three potential Loss-of-Coolant Accident (LOCA) scenarios in the General Electric Simplified Boiling Water Reactors (SBWR) a set of Phenomena Identification and Ranking Tables (PIRT) is presented. The selected LOCA scenarios are typical for the c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f7a53303956603bf0336192013f897a6
https://doi.org/10.2172/594510
https://doi.org/10.2172/594510
This report documents the THATCH code, which can be used to model general thermal and flow networks of solids and coolant channels in two-dimensional r-z geometries. The main application of THATCH is to model reactor thermo-hydraulic transients in Hi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7c97840e8f7139541c24af9285961208
https://doi.org/10.2172/6239042
https://doi.org/10.2172/6239042
The solution of a two-dimensional freezing problem including convection effects in the liquid region
Autor:
Simon Ostrach, P.G. Kroeger
Publikováno v:
International Journal of Heat and Mass Transfer. 17:1191-1207
To simulate a continuous casting process the temperature and flow field during solidification of a pure metal in a moving slab is considered. The analysis includes natural convection effects in the liquid pool. Strong natural convection flows occur a
Autor:
P.G. Kroeger, Novak Zuber
Publikováno v:
International Journal of Heat and Mass Transfer. 11:211-233
An evaluation of the effects of various parameters on the ability to predict accurately the volumetric vapor concentration in subcooled boiling is presented. It is shown that: (1) the distribution parameter is of major importance as thermodynamic equ
Autor:
P.G. Kroeger
The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant rea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6a23778e00bcfd2bff19123e0cdeb847
https://doi.org/10.2172/950423
https://doi.org/10.2172/950423
Autor:
P.G. Kroeger
The transient propagation of a phase-change front during the depressurization of a subcooled liquid has been analyzed for the case of thermal equilibrium without friction or heat addition, using wave diagram solutions. Various modes of phase-change f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e9598723d17460c7e80501987ca08236
https://doi.org/10.2172/6354273
https://doi.org/10.2172/6354273
Autor:
P.G. Kroeger, G.J. Van Tuyle
In view of the recent shift in emphasis of the DOE/Industry HTGR development efforts to smaller modular designs it became necessary to review the modelling needs and the codes available to assess the safety performance of these new designs. This repo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8b7eb13ea6f79c49d24c43b670046969
https://doi.org/10.2172/6131128
https://doi.org/10.2172/6131128
Modeling of water/steam ingress into the primary (helium) cooling circuit of a High Temperature Gas-Cooled Reactor (HTGR) is described. This modeling was implemented in the MINET Code, which is a program for analyzing transients in intricate fluid fl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a6d0b27164dc88b0d92c73830487f333
https://doi.org/10.2172/6342972
https://doi.org/10.2172/6342972
In support of the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) has performed independent analyses of two advanced Liquid Metal Reactor (LMR) concepts. The designs, sponsored by the US Department of Energy (DOE), the Po
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5e72ab50a6c31c2757f097a1fb4db064
https://doi.org/10.2172/5491968
https://doi.org/10.2172/5491968