Thermal-hydraulic analysis for wire-wrapped PWR cores

Nuclear Engineering and Design

Volumn 239, Issue 8, 2009, Pages 1461-1470

  Diller, P ^a   Todreas, N ^b   Hejzlar, P ^b  

^a GENERAL ELECTRIC COMPANY   (United States)

^b MASSACHUSETTS INSTITUTE OF TECHNOLOGY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CLADDING TEMPERATURES; CRITICAL HEAT FLUX; DESIGN LIMITS; FLOW ACCIDENT; FLOW-INDUCED VIBRATION; FRETTING WEAR; GRID SPACER; HEXAGONAL ARRAYS; HYDRIDE FUEL; LOWER PRESSURES; NEUTRONIC; NUCLEAR TECHNOLOGY; POWER INCREASE; THERMAL HYDRAULICS; THERMAL-HYDRAULIC ANALYSIS; THERMAL-HYDRAULIC PERFORMANCE; TRANSIENT THERMAL-HYDRAULIC; WORK FOCUS;

ACCIDENTS; DESIGN; DROPS; HEAT FLUX; LOSS OF COOLANT ACCIDENTS; PRESSURE DROP; PRESSURIZED WATER REACTORS; SMALL NUCLEAR REACTORS; TABLE LOOKUP; TRANSIENT ANALYSIS; WIRE; ZIRCONIUM ALLOYS;

HYDRAULICS;

EID: 67349226102     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.01.015     Document Type: Article

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