Assessment experiments on intermediate- and high-burnup test rods

Nuclear Safety

Volumn 37, Issue 4, 1996, Pages 372-387

  Ria Simulation, O ^a,b   Montgomery, R O ^a,b   Rashid, Y R ^a,b   Ozer, O ^a,b   Yang, R L ^a,b  

^a ANATECH CORP   (United States)

^b ELECTRIC POWER RESEARCH INSTITUTE   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CAPSULE DRIVER CORES (CDC); FUEL BURNUP; FUEL RODS; NUCLEAR SAFETY RESEARCH REACTORS (NSRR); REACTIVITY INITIATED ACCIDENTS (RIA); SPECIAL POWER EXCURSION REACTOR TEST (SPERT);

COMPUTER SIMULATION; COOLANTS; FAILURE ANALYSIS; LIGHT WATER REACTORS; NUCLEAR FUEL CLADDING; REACTIVITY (NUCLEAR); RESEARCH REACTORS;

NUCLEAR REACTOR ACCIDENTS;

NUCLEAR FUEL;

ENTHALPY; IRRADIATION; NUCLEAR ACCIDENT; NUCLEAR ENERGY; NUCLEAR REACTOR; PRIORITY JOURNAL; RADIATION PROTECTION; REVIEW; TEMPERATURE SENSITIVITY;

EID: 0030252288     PISSN: 00295604     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article

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