Published September 1, 2018 | Version v1
Report Metadata-only

Overview of Aluminum Oxide Prediction Models for High Power Research Reactors

Creators

  • 1. Argonne National Laboratory (ANL), Argonne, IL (United States)

Description

UMo/Al dispersion fuel clad with aluminum alloy cladding is a primary candidate fuel form that is being developed for high power research and test reactors including European high power research reactors (EUHPRR). Oxidation of cladding is considerable due to high power application. One of the objectives of this report is to review the existing oxide prediction models and heat transfer correlations at cladding surface.

Availability note (English)

Available from https://www.osti.gov/servlets/purl/1480535; https://www.osti.gov/biblio/1480535; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period

Additional details

Identifiers

URL
https://www.osti.gov/servlets/purl/1480535; https://www.osti.gov/biblio/1480535;
DOI
10.2172/1480535;

Publishing Information

Imprint Pagination
66 p.
Report number
OSTIID--1480535

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
51103059
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
ALUMINIUM ALLOYS; ALUMINIUM OXIDES; CLADDING; HEAT TRANSFER; RESEARCH REACTORS
Descriptors DEC
ALLOYS; ALUMINIUM COMPOUNDS; CHALCOGENIDES; DEPOSITION; ENERGY TRANSFER; OXIDES; OXYGEN COMPOUNDS; REACTORS; RESEARCH AND TEST REACTORS; SURFACE COATING

Optional Information

Contract/Grant/Project number
AC02-06CH11357
Funding organization
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20). Office of Material Management and Minimization NA-23 Reactor Conversion Program (United States)
Secondary number(s)
ANL-RTR/TM--18/10