Zobrazeno 1 - 10
of 74
pro vyhledávání: '"Neil E. Todreas"'
Publikováno v:
Nuclear Engineering and Design. 335:356-373
The Cheng and Todreas (detailed) correlation (CTD) for wire-wrapped rod bundle friction factor published in 1986 has been identified in Chen et al. (2014) as the most used correlation for design and safety analyses for the Generation IV Sodium Fast R
Autor:
Jacopo Buongiorno, Neil E. Todreas, Jason Florek, Jared Conway, Arthur Birch, John Halsema, Tom Isdanavich, Chris Guryan, Michael W. Golay
Publikováno v:
Prof. Buongiorno via Chris Sherratt
This research has investigated the effectiveness of the proposed security plan for the ONP-300 through the use of a simulation software developed by ARES Security Corporation which evaluates the plant design and security plan. This paper updates the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cad785fdba019ba27e1377ec1b70b90b
https://hdl.handle.net/1721.1/126733
https://hdl.handle.net/1721.1/126733
Publikováno v:
Prof. Buongiorno via Chris Sherratt
The Offshore Floating Nuclear Plant (OFNP) integrates an advanced light water reactor into a cylindrical, double-hull, floating platform. It offers a series of potential benefits in economics and safety. The 300-MW(electric) version, named OFNP-300,
Publikováno v:
Nuclear Engineering and Design. 370:110910
For the occasion of celebrating the 40th anniversary of the NURETH conference series, we present a brief overview of our work on the thermal-hydraulics of wire-wrapped rod bundles over these past four decades. In this context, this short technical no
Publikováno v:
Other repository
A new offshore floating nuclear plant (OFNP) concept with high potential for attractive economics and an unprecedented level of safety is presented. OFNP creatively combines state-of-the-art light water reactors and floating platforms similar to thos
Autor:
Neil E. Todreas
Publikováno v:
Nuclear Engineering and Design. 354:110250
Publikováno v:
Nuclear Engineering and Design. 263:406-410
The Cheng and Todreas (1986) correlation is widely used for calculation of pressure loss in wire wrapped hexagonal rod bundles. Recent application indicates that the transition region friction factor calculated causes reverse pressure drop as flow ra
Publikováno v:
Nuclear Engineering and Design. 340:414
Publikováno v:
Nuclear Engineering and Design. 257:1-11
This paper presents correlations developed for predicting critical heat flux (CHF) and pressure drop in tubes containing multiple short-length twisted tapes (MSLTT) at operating conditions applicable to pressurised water reactors (PWRs). The specific
Publikováno v:
Nuclear Engineering and Design. 239:2612-2625
A 2400 MWth liquid-salt cooled flexible conversion ratio reactor was designed, utilizing the ternary chloride salt NaCl–KCl–MgCl 2 (30–20–50%) as coolant. The reference design uses a wire-wrapped, hexagonal lattice core, and is able to achiev