Ionising radiation dose calculations for the release of 131I during accident conditions at the SAFARI-1 materials test reactor
Date
2011-03-14
Authors
Bekker, Willem Adriaan
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Abstract
This study demonstrates how the Monte Carlo N-Particle (MCNP) radiation transport
code can be used as a contribution to the family of Safety Analysis tools for Research
Reactors. Since Research Reactors are used worldwide over a wide range of research
and commercial applications it can be justified that effort must be spent to improve on
safety analysis. While the advantages of these installations to society are widely
recognized, it is still necessary that safety analysis provides the necessary assurance that
these installations do not cause an undue risk to society. A Materials Test Reactor
(MTR) is used as an example to describe the Safety Analysis steps that need to be done,
limited to the reactor and its building. A radioactive inventory in the reactor core is
determined. For further evaluation of the effects of the release due to a hypothetical
accident in such a reactor, the 131I radioisotope is chosen to demonstrate the capabilities
of the MCNP code. A 131I cloud resulting from the release is simulated together with an
MCNP model of the reactor building. Personnel in the proximity of the 131I cloud for
short times, either due to emergency actions or accidental entrapment, are also
modelled. The external photon whole-body doses and -decay (electron) skin doses are
determined. The MCNP code results are also benchmarked against another method.
The findings show that the method presented in the study could be used to predetermine
emergency actions that could be incorporated into emergency planning and
even into design of a new research reactor. This is substantiated by the conclusion that
only the external photon dose could result in unacceptable doses above 500 mSv for
short exposure times. The study concludes that the MCNP code can be used effectively
for Safety Analyses and leaves the opportunity open to expand the use of the code to
other fields related to research reactors.