"The Safety Analysis Report, SAR, is very important to commercial and research nuclear reactors alike and should be considered a living document. The Nuclear Regulatory Commission has instituted changes over the past few years to rely more on the SAR for the processes of licensing, relicensing, and uprating in power. As result of these changes the NRC has streamlined the licensing processes such that the length of time expended for application approval is shorter and in addition, easier for facilities.
The University of Missouri-Rolla Reactor, UMRR, is up for relicensing January 2005 and has begun to review and revise its SAR to update to current NRC standards. A preliminary investigation into the possibility of a power uprate has also begun. As a part of this investigation, PARET-ANL and CONVEC were used to analyze accident scenarios at the currently licensed power of 200 kWt and at possible uprate powers of 400 kWtand 500 kWt . CONVEC is a natural convection modeling code and PARET is a code used to investigate reactor reactivity transients. Due to the NRC permitting credit to be taken for a reactor SCRAM function, the hypothetical severe accident scenarios have been evaluated with the use of the UMRR safety channel SCRAM set-point of 150% of licensed power.
Several improbable, but significant accident scenarios are expected in the SAR. The first accident is an insertion of excess reactivity that assumes a fuel element being placed accidentally next to the UMRR core. For the second accident, a loss of coolant accident (LOCA) in which all coolant is assumed to drain was evaluated. As a final accident, a startup accident was analyzed in which the UMRR's control elements were assumed to uncontrollably withdraw from the core. Each of these accidents is important to analyze due to the risk of fuel cladding failure that could potentially result in the release of fission products. The analysis described in this thesis proves that the UMRR would maintain fuel integrity during the aforementioned accident scenarios and thus avert the release or fission products "--Abstract, page iii.
Mueller, Gary Edward, 1954-
Mining and Nuclear Engineering
M.S. in Nuclear Engineering
University of Missouri--Rolla
x, 131 pages
© 2004 Christopher Michael Carroll, All rights reserved.
Thesis - Restricted Access
Nuclear reactors -- Safety measures -- Evaluation
Nuclear reactor accidents -- Analysis
Risk assessment -- United States
Print OCLC #
Electronic OCLC #
Link to Catalog Record
Electronic access to the full-text of this document is restricted to Missouri S&T users. Otherwise, request this publication directly from Missouri S&T Library or contact your local library.http://merlin.lib.umsystem.edu/record=b5123685~S5
Carroll, Christopher M., "Using PARET and CONVEC to perform accident analysis of the University of Missouri-Rolla Nuclear Reactor" (2004). Masters Theses. 2488.
KINETICS AND THERMOHYDRAULIC EQN. FOR PARET
App_E.pdf (929 kB)
KINETICS AND THERMOHYDRAULIC EQN FOR CONVEC
App_P.pdf (1160 kB)
MTR FUEL DESCRIPTION ARTICLE
App_Q.pdf (1536 kB)
EXCERPTS ABOUT SPERT EXPERIMENTS
App_R.pdf (1927 kB)
CHAPTER 13 OF NUREG 1537 PART 1
App_S.pdf (4883 kB)
CHAPTER 13 OF NUREG 1537 PART 2
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