atw - International Journal for Nuclear Power | 2.2024
Internationale Entwicklungen und Trends
Internationale Entwicklungen und Trends
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56<br />
<br />
Environment and Safety<br />
population. These codes can estimate the doses and<br />
health effects <strong>for</strong> different scenarios and locations and<br />
help to identify the appropriate protective actions and<br />
emergency planning zones (EPZs) <strong>for</strong> the facility [24] .<br />
One of the consequence assessment methods that is<br />
used by the USNRC and other regulatory bodies is the<br />
MACCS code which stands <strong>for</strong> MELCOR Accident<br />
Consequence Code System, and it is a suite of programs<br />
that can model the atmospheric dispersion of radionuclides,<br />
the deposition and resuspension of contaminants,<br />
the ingestion of contaminated food and<br />
water, the evacuation and relocation of people, and the<br />
economic costs and health risks of the accident. MACCS<br />
can be used to per<strong>for</strong>m probabilistic risk assessments<br />
(PRAs) that account <strong>for</strong> the frequency and severity of<br />
different accident sequences, and to determine the EPZ<br />
size based on the dose criteria and the protective action<br />
guidelines [79] .<br />
5.5 The iPWR stand-alone case<br />
C. Zeliang et al. [86] noted that over the years, the iPWR<br />
SMR type has stood out from the rest of the small<br />
modular reactors because it integrates the major of<br />
known primary system components to inherently<br />
eliminate or lower potential accident initiators and<br />
employ simplified Passive Safety Systems to counter<br />
and mitigate the remaining accident initiators. These<br />
design aspects are substantiated by substantial operating<br />
experience (PWRs) and legacy PWR designs. The<br />
iPWR design characteristics offers the potential to<br />
eliminate some potential accidents initiators (e.g.,<br />
large loss of coolant accidents (LOCAs), control rod<br />
ejection accident), decrease the probability of failure<br />
<strong>for</strong> remaining initiators; and enhanced features to<br />
mitigate the consequences [87], [88], [89], [90], [91] .<br />
To deploy iPWR Small Modular Reactors soon, as part<br />
of emergency preparedness and response plan, it is<br />
very important to assess their potential radiological<br />
impact and emergency planning zones. C. Zeliang and<br />
his co-authors [86] in their research work, tried to<br />
provide an analysis and estimation of the envelope of<br />
the potential impact from a severe accident in an iPWR.<br />
The source term was calculated from the solution<br />
of the lumped aerosol concentration equation in the<br />
containment, by using different approaches <strong>for</strong><br />
estimating the various parameters. The first approach<br />
comprised a straight<strong>for</strong>ward use of the methodology<br />
and parameters used <strong>for</strong> large reactors differing only<br />
in the lower power level of an iPWR. To account <strong>for</strong> the<br />
anticipated enhanced aerosol retention in the containment<br />
and the slower (in time) core damage progression<br />
in case of iPWR, two additional approaches<br />
were also used.<br />
6. Conclusions<br />
Determination of the Emergency Planning Zone<br />
surrounding a nuclear power station reflects both the<br />
technical aspects and the associated (regulatory)<br />
compliance – <strong>for</strong>emost safety-in-design and operations.<br />
The necessity of a defined EPZ gives the public<br />
assurance and assures the careful consideration of the<br />
impact of accidents involving NPPs. EPZs are required<br />
under various regulatory and governmental frameworks<br />
at all NPPs stations. This expectation will not be<br />
any different <strong>for</strong> Micro to Small Modular Reactors, in<br />
both new sites and existing sites. For SMRs/MMRs,<br />
smaller EPZ is expected, since potentially, the “sourceterm”<br />
is smaller than conventional (large) NPPs. Prior<br />
to the recent certified SMR designs, the EPZ was<br />
conservatively based on recommendations by an<br />
expert panel. Some 40+-years later some to many<br />
( national) regulatory frameworks remain unchanged<br />
(except incremental developments) with respect to<br />
the EPZ. In brief, these perspectives summarize the<br />
spectrum of aspects, as follows:<br />
⁃ Insights from all the papers collated offer a holistic<br />
perspective on EPZ requirements <strong>for</strong> large reactors<br />
applied to, and SMRs (including MMRs) going<br />
<strong>for</strong>ward. Together, they provide a comprehensive<br />
understanding of the challenges and solutions<br />
associated with determination of the EPZ <strong>for</strong> (alltypes<br />
of) SMRs – importantly integrating both<br />
national regulatory expectations and technical<br />
considerations. They collectively contribute to the<br />
ongoing dialogue on ensuring the safety-in-design<br />
of nuclear power, particularly in the context of<br />
Small Modular Reactors.<br />
⁃ When implementing SMR, an EPZ is a crucial factor<br />
to consider since it is critical to build trust and thus<br />
public acceptance in this new technology. Public<br />
acceptance or social license take time, effective<br />
communication, transparency, engagement, and<br />
continuous education [92], [93], [94] .<br />
⁃ The existing research focuses on specific designs<br />
that may establish emergency planning zones <strong>for</strong><br />
Small Modular Reactors. Some regulators intend to<br />
develop a technology neutral, open access approach<br />
used to establish the EPZ of SMRs.<br />
⁃ In some new nuclear power nations with a weak<br />
regulator, the vendor determines the EPZ of the<br />
plant. This is because the vendor has more<br />
experience and knows the best criteria to determine<br />
the emergency planning zone.<br />
⁃ It is also important to note that the EPZ <strong>for</strong> SMRs is<br />
scalable depending on the results of accident<br />
analysis, the technology type, novel features, and<br />
specific design criteria and policy factors which<br />
vary amongst different countries.<br />
⁃ The safety culture in the SMR industry needs to be<br />
explored deeply to better understand all the safety<br />
systems in place in case of an SMR related<br />
emergency.<br />
Acknowledgement.<br />
The co-authors note and thank Mr. Anthime Farda,<br />
World <strong>Nuclear</strong> University Summer Institute graduate,<br />
<strong>for</strong> providing references regarding the French<br />
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