Preparing the high flux isotope reactor for conversion to low enriched uranium fuel - extending cycle burnup

R. T. Primm, David Chandler

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

Reactor performance studies have been completed for conceptual plate designs and show that maintaining reactor performance while converting HFIR from 235 high enriched to low enriched uranium (20 wt % 235U) fuel requires extending the end-of-life burnup value for HFIR fuel from the current nominal value of 2200 MWD to 2600 MWD. The current fuel fabrication procedure is discussed and changes that would be required to this procedure are identified. Design and safety related analyses that are required for the certification of a new fuel are identified. Qualification tests and comments regarding the regulatory approval process are provided along with a conceptual schedule.

Original languageEnglish
Title of host publicationAmerican Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Pages1113-1120
Number of pages8
StatePublished - 2009
EventAmerican Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV - Hilton Head Island, SC, United States
Duration: Apr 12 2009Apr 15 2009

Publication series

NameAmerican Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Volume2

Conference

ConferenceAmerican Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Country/TerritoryUnited States
CityHilton Head Island, SC
Period04/12/0904/15/09

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