Work

Nuclear fuel rod behavior during LOFT experiment L2-2

Year: 1979

Type: article

Abstract: The Loss-of-Fluid Test (LOFT) Program is providing data to evaluate analytical models used to predict the thermal-hydraulic and fuel rod response of a pressurized water reactor (PWR) under loss-of-coolant accident (LOCA) conditions. The fuel rod response for the first nuclear loss-of-coolant experiment (LOCE), LOCE L2-2, is summarized.

Source: University of North Texas Digital Library (University of North Texas)

Authors: Tolman, E. L., Niebruegge, D. A., Prassinos, P. G.

Institution: Idaho National Laboratory

Language: English

Topic: Nuclear Engineering Thermal-Hydraulics

Subfield: Nuclear Energy and Engineering

Field: Energy

Domain: Physical Sciences

Open Access status: green

OpenAlex ID: W1600226506

FWCI:

Cites:

Cited by: 1

Related to: 10