Modern design and safety analysis of the University of Florida Training Reactor

•A new safety analysis of the University of Florida Training Reactor is presented.•This analysis uses modern codes and replaces the NRC approved analysis from 1982.•Reduction in engineering margin confirms that the UFTR is a negligible risk reactor.•Safety systems are not required to ensure that saf...

Full description

Saved in:
Bibliographic Details
Published inNuclear engineering and design Vol. 286; pp. 89 - 93
Main Authors Jordan, K.A., Springfels, D., Schubring, D.
Format Journal Article
LanguageEnglish
Published Elsevier B.V 01.05.2015
Subjects
Online AccessGet full text

Cover

Loading…
More Information
Summary:•A new safety analysis of the University of Florida Training Reactor is presented.•This analysis uses modern codes and replaces the NRC approved analysis from 1982.•Reduction in engineering margin confirms that the UFTR is a negligible risk reactor.•Safety systems are not required to ensure that safety limits are not breached.•Negligible risk reactors are ideal for testing digital I&C equipment. A comprehensive series of neutronics and thermal hydraulics analyses were conducted to demonstrate the University of Florida Training Reactor (UFTR), an ARGONAUT type research reactor, as a negligible risk reactor that does not require safety-related systems or components to prevent breach of a safety limit. These analyses show that there is no credible UFTR accident that would result in major fuel damage or risk to public health and safety. The analysis was based on two limiting scenarios, whose extremity bound all other accidents of consequence: (1) the large step insertion of positive reactivity and (2) the release of fission products due to mechanical damage to a spent fuel plate. The maximum step insertion of positive reactivity was modeled using PARET/ANL software and shows a maximum peak fuel temperature of 283.2°C, which is significantly below the failure limit of 530°C. The exposure to the staff and general public was calculated for the worst-case fission product release scenario using the ORIGEN-S and COMPLY codes and was shown to be 6.5% of the annual limit. Impacts on reactor operations and an Instrumentation & Control System (I&C) upgrade are discussed.
Bibliography:ObjectType-Article-1
SourceType-Scholarly Journals-1
ObjectType-Feature-2
content type line 23
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2015.01.019