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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 />

Ausgabe 2 › März

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