Full-length fuel rod behavior under severe accident conditions

Technical Report · Tue Dec 01 00:00:00 EST 1992

DOI:https://doi.org/10.2172/7042819· OSTI ID:7042819

Lombardo, N J; Lanning, D D; Panisko, F E ^[1]

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1. Pacific Northwest Lab., Richland, WA (United States)

This document presents an assessment of the severe accident phenomena observed from four Full-Length High-Temperature (FLHT) tests that were performed by the Pacific Northwest Laboratory (PNL) in the National Research Universal (NRU) reactor at Chalk River, Ontario, Canada. These tests were conducted for the US Nuclear Regulatory Commission (NRC) as part of the Severe Accident Research Program. The objectives of the test were to simulate conditions and provide information on the behavior of full-length fuel rods during hypothetical, small-break, loss-of-coolant severe accidents, in commercial light water reactors.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 7042819
• Report Number(s): NUREG/CR-5876; PNL-8023; ON: TI93005718
• Country of Publication: United States
• Language: English

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