Methodology to Ascertain Core Recriticality Following a Severe Fission Reactor Accident

Joseph John Bevelacqua

Abstract


Recriticality concerns have been expressed following severe power reactor accidents, involving fuel melting and possible core relocation out of the reactor vessel.  Analyses of reactor coolant liquid samples must carefully evaluate fission isotope activities when assessing the possibility of a recriticality.  Assessments should consider the criticality duration, sampling time, sampling location, and core operating history to provide an accurate determination of a recriticality.  By considering these factors, the 131I/137Cs activity ratio can lead to a determination if a recriticality occurred.


Keywords


Recriticality analysis; reactor coolant samples; TMI-2 accident; Fukushima Daiichi Accident

References


GPU Nuclear Corporation Three Mile Island Nuclear Station Unit 2 Defueling Completion Report, Revision 4. Middletown, PA: GPU Nuclear Corporation (1990).

Bevelacqua, J. J. Applicability of Health Physics Lessons Learned from the Three Mile Island Unit-2 Accident to the Fukushima Daiichi Accident, Journal of Environmental Radioactivity 105, 6 (2012).

Matsui, T. Deciphering the Measured Ratios of Iodine-131 to Cesium-137 at the Fukushima Reactors (2011), available at arXiv:1105.0242v3 [nucl-th] accessed on August 5, 2012.

U. S. Nuclear Regulatory Commission. Recriticality in a BWR Following a Core Damage Event. Washington DC, U. S. Government Printing Office, NUREG/CR-5653 (1990).

The National Diet of Japan, The Fukushima Nuclear Accident Independent Investigation Commission, The National Diet of Japan, Tokyo (2012).

Bevelacqua, J. J. Contemporary Health Physics: Problems and Solutions. 2nd edition Weinheim, Wiley-VCH (2009).

Bevelacqua, J. J. Basic Health Physics: Problems and Solutions. 2nd edition Weinheim, Wiley-VCH (2010).

Knief R. A. Nuclear engineering—theory and technology of commercial nuclear power. 2nd edition. Washington, DC, Hemisphere Publishing Corporation (1992).

U. S. Nuclear Regulatory Commission. Reactor Safety Study: An assessment of Accident Risks in U.S. Commercial nuclear Power Plants. Washington DC, U. S. Government Printing Office, WASH-1400, (1975).

International Nuclear Data Committee Report, Handbook of Nuclear Data for Safeguards Database Extensions, August 2008, INDC(NDS)-0534, International Atomic Energy Agency, Vienna (2008).

Glasstone, S. Energy Deskbook, DOE/IR/05114-1. US Department of Energy, Washington, DC (1982).

IAEA Report, Thorium fuel cycle – Potential benefits and challenges, IAEA-TECDOC-1450, International Atomic Energy Agency, Vienna (2005).

IAEA Report, International Evaluation of Neutron Cross-Section Standards, STI/PUB/1291, International Atomic Energy Agency, Vienna (2007).

Olander, D. R. Fundamental Aspects of Nuclear Reactor Fuel Elements, TID-26711-P1. US Department of Energy, Washington, DC (1976).


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