Work

MELCOR Accident Progression and Source Term Analysis for a Fluoride High-Temperature Reactor.

Year: 2022

Type: article

Abstract: UCO TRISO thermal failure characteristics were not available, so UO 2 TRISO diffusivity and UO 2 failure data were used.Both are changeable through user input with design-specific data.* UCO TRISO thermal failure characteristics were not available, so UO 2 TRISO diffusivity and UO 2 failure data were used.Both are changeable through user input with design-specific data.

Source: OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)

Author: Wagner, Kenneth

Language: English

Topic: Nuclear reactor physics and engineering

Subfield: Aerospace Engineering

Field: Engineering

Domain: Physical Sciences

Open Access status: green

OpenAlex ID: W4309979481

FWCI: 0.111

Cites:

Cited by: 1

Related to: 10