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atw - International Journal for Nuclear Power | 06/07.2019

The atw reports on developments and trends in all major areas of nuclear power technology and the nuclear power industry. The international topicality and competence of its coverage make the atw monthly a valuable source of information and, in this way, also an important aid in decision making. Its rich background of reporting, and the contributions by competent authors make atw a valueable source of information.

The atw reports on developments and trends in all major areas of nuclear power technology and the nuclear power industry. The international topicality and competence of its coverage make the atw monthly a valuable source of information and, in this way, also an important aid in decision making. Its rich background of reporting, and the contributions by competent authors make atw a valueable source of information.

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<strong>atw</strong> Vol. 64 (2019) | Issue 6/7 ı June/July<br />

SERIAL | MAJOR TRENDS IN ENERGY POLICY AND NUCLEAR POWER 346<br />

if necessary implementation of properties <strong>for</strong> new heat<br />

pipe working fluids,<br />

pp<br />

single/two phase flow natural convection, flow<br />

instabilities and transition range between single and<br />

two natural convection,<br />

pp<br />

passive safety systems (special components, start-up<br />

behavior, mutual interaction of different passive safety<br />

systems or trains of one passive safety system, ­extension<br />

of the scope of correlations <strong>for</strong> containment heat<br />

transfer)<br />

pp<br />

check-valves, in which the opening cross section and<br />

the associated <strong>for</strong>m loss is calculated dependent on the<br />

pressure difference up- and downstream the valve,<br />

pp<br />

3D models <strong>for</strong> water pools/environment (ultimate<br />

containment heat sink), temperature and velocity<br />

fields, stratification,<br />

pp<br />

heat transfer at bundle surfaces at free convection,<br />

subcooled or saturated boiling conditions,<br />

pp<br />

steam condensation at containment walls, structures<br />

and internals especially <strong>for</strong> the case of small break<br />

LOCA, inertised containments or containments<br />

operated at near vacuum conditions,<br />

pp<br />

new coupling (strategy) between ATHLET and COCOSYS,<br />

pp<br />

infinite passive containment cooling to an ultimate heat<br />

sink in ocean environment (influence of seawater,<br />

mussel growth, etc.),<br />

pp<br />

heat transfers of horizontally arranged containment<br />

in large water pools or the ocean at RA-numbers of<br />

approx. 1015.<br />

The above mentioned, open issues shall be processed and<br />

closed with national and international research alliances.<br />

One example is the EU project ELSMOR (Towards European<br />

Licensing of Small Modular Reactors), which has received<br />

approval <strong>for</strong> grant agreement preparations under the<br />

European Union’s Horizon 2020 research and innovation Literature<br />

programme. Scheduled to be launched in the summer of<br />

2019, a total of 15 organisations from 8 countries will<br />

participate in ELSMOR, to which the EU has granted EUR<br />

3.5 million. GRS leads in ELSMOR two important work<br />

packages. The consortium consists of support organisations<br />

of European TSOs, universities, power companies,<br />

and some of the developers of a French SMR design I-150<br />

[CHJ-17]. ELSMOR is developing systematic methods <strong>for</strong><br />

the safety assessments of new and innovative reactors<br />

(here especially SMRs). The project shall contribute that<br />

European experimental infrastructures and modelling/­<br />

evidence tools will be ready <strong>for</strong> use in nuclear licensing<br />

procedures [VTT-19].<br />

5 Summary<br />

Small modular reactors are one interesting option <strong>for</strong> new<br />

builds in almost all countries worldwide continuing to use<br />

nuclear energy <strong>for</strong> commercial electricity production.<br />

­Currently four SMRs are in operation, further six SMRs are<br />

under construction and eleven at an advanced stage of<br />

planning. Different European countries (e.g. the United<br />

Kingdem, Russia, Poland) are planning to build and<br />

operate SMRs. Even after nuclear phase-out the German<br />

Federal government would like to assert legitimate nuclear<br />

safety and/or security interests, e.g. by promoting comprehensive<br />

safety reviews and ambitious binding targets<br />

<strong>for</strong> the new builds (including SMRs) in our neighborhood.<br />

The Gesellschaft für Anlagen- und Reaktorsicherheit<br />

(GRS) gGmbH as the main German technical support<br />

organization in nuclear safety <strong>for</strong> the German government,<br />

has per<strong>for</strong>med a Study on Safety an <strong>International</strong><br />

Development on SMR published in 2015 (GRS-376). In this,<br />

numerous trends of current SMR development were<br />

­identified. They are presented in this publication. The<br />

modelling gaps of the GRS simulation chain were compiled<br />

and a strategy <strong>for</strong> their closure was developed. The main<br />

findings are: The safety level was increased e.g. by an<br />

advanced, conservative design, implementation of new<br />

safety features (e.g. passive safety systems) and the<br />

­exclusion of accidents (e.g. LBLOCA, control rod ejection).<br />

There<strong>for</strong>e, SMR could be – if proven by safety analyses –<br />

among the safest nuclear equipment ever made. Factory<br />

fabrication minimizes the (financial) risk of delay in<br />

construction. Competitiveness e.g. with gas power plants<br />

requires the construction of a large number of identical<br />

SMR units worldwide. Prerequisites <strong>for</strong> this are that all<br />

entry barriers have been overcome like series production<br />

in factories, which are currently not existing, and a<br />

worldwide harmonization of rules and regulations and<br />

recognition of licenses of <strong>for</strong>eign nuclear regulators.<br />

­However, currently published figures are fraught with<br />

large uncertainties and not yet reliable. Independently of<br />

the previously mentioned open points, which are irrelevant<br />

from TSO’s point of view, GRS will further develop and<br />

validate its nuclear simulation chain. This allows to<br />

successfully apply the GRS simulation chain in nuclear<br />

licenses procedures and independent safety analyses also<br />

<strong>for</strong> SMRs.<br />

Acknowledgement<br />

This article contains results of the research project Study<br />

of Safety and <strong>International</strong> Development of SMR (grant<br />

number RS1521), which was funded by the German<br />

Federal Ministry <strong>for</strong> Economic Affairs and Energy (BMWi).<br />

ıı<br />

ARH-171 Army Engineer History. Army nuclear <strong>Power</strong> Program Virtual Exhibit, April 2017. https://<br />

armyengineerhistory.dodlive.mil/anpp/, last visit: 23.05.2019<br />

ıı<br />

ARH-172 Army Engineer History. Experimental Reactors, April 2017.<br />

https://armyengineerhistory.dodlive.mil/anpp/experimental-reactors/, last visit: 23.05.2019<br />

ıı<br />

ARV-17 V. Artisiuk. SMR Technology Development in Russia and Capacity Building Supports<br />

<strong>for</strong> Embarking Countries, IAEA Technical Meeting on Technology Assessment of Small Modular<br />

Reactors <strong>for</strong> Near Term Deployment, October 02-05, 2017, Tunis (Tunisia).<br />

ıı<br />

ATG-11 Atomgesetz. Dreizehntes Gesetz zur Änderung des Atomgesetzes (13. AtGÄndG)<br />

vom 11. Juli 2011, Bundesgesetzblatt Teil 1, Nr. 43 vom 05.08.2011.<br />

ıı<br />

BAJ-18 J. Bailey. NuScale – Blazing the Trail <strong>for</strong> Modular SMRs, Energy Huntsville, January 16,<br />

2018.<br />

ıı<br />

BFE-18 Bundesamt für kerntechnische Entsorgung. Bekanntmachung gemäß §7 Absatz 1 c<br />

Atomgesetz (AtG), Jahresmeldung 2018, 01.04.2019. https://www.bfe.bund.de/<br />

SharedDocs/Downloads/BfE/DE/berichte/kt/elektrizitaetsmenge-2018.html;<br />

jsessionid=2A7282737BADE20FBAB532ED BA614995.1_cid382, last visit: 23.05.2019<br />

ıı<br />

BR-18 Bundesregierung. Ein neuer Aufbruch für Europa, eine neue Dynamik für Deutschland,<br />

ein neuer Zusammenhalt für unser Land, Koalitionsvertrag zwischen CDU, CSU und SPD,<br />

19. Legislaturperiode, 12.03.2018, Berlin (Germany).<br />

ıı<br />

BMU-15 Bundesministerium für Umwelt, Naturschutz, Bau und Reaktorsicherheit. Sicherheitsan<strong>for</strong>derungen<br />

für Kernkraftwerke, in der Fassung vom 03.03.2015, Bundesanzeiger AT 30.03.2015 B2.<br />

ıı<br />

BUS-15 S. Buchholz, A. Krüssenberg, A. Schaffrath. Safety and <strong>International</strong> Development of Small<br />

Modular Reactors (SMR) – A Study of GRS, <strong>atw</strong> <strong>International</strong> <strong>Journal</strong> <strong>for</strong> <strong>Nuclear</strong> <strong>Power</strong>, Vol. 60<br />

(2015), Issue 11, pp. 645 – 653.<br />

ıı<br />

BUS-16 S. Buchholz, A. Schaffrath, A. Krüssenberg. Study of Safety and <strong>International</strong> Development<br />

of SMR. EUROSAFE 2016, November 07-08, Munich (Germany).<br />

ıı<br />

CHE-<strong>06</strong> S.C. Chetal, et al. The Design of the Prototype Fast Breeder Reactor, <strong>Nuclear</strong> Engineering<br />

and Design Vol. 236 (20<strong>06</strong>), pp. 852 – 860.<br />

ıı<br />

CHJ-17 J. Chenais. SMR Technology The French Approach, IAEA Technical Meeting on Technology<br />

Assessment of Small Modular Reactors <strong>for</strong> Near Term Deployment, October 2-5, 2017, Tunis (Tunisia).<br />

ıı<br />

COI-18 Competitive India. India’s first Indigenously Developed Prototype Fast Breeder Reactor to<br />

achieve Criticality in 2019, 22.09.2018. http://competitiveindia.com/currentaffairs/2018/09/22/<br />

indias-first-indige-nously-developed-prototype-fast-breeder-reactor-to-achieve-criticality-in-2019/,<br />

last visit: 23.05.2019<br />

ıı<br />

DEA-14 J. De Amicis, et. al. Experimental and Numerical Study of the Laminar Flow in Helically Coiled<br />

Pipes, Progress in <strong>Nuclear</strong> Engineering, Vol. 76, 2014, pp. 2<strong>06</strong> – 215<br />

ıı<br />

DIX-13 A. Dixit et al. Start-up Transient Test Simulation with and without Void-Reactivity Feedback<br />

<strong>for</strong> a Two-Phase Natural Circulation Reactor, <strong>Nuclear</strong> Engineering and Design, Vol. 265 (2013),<br />

pp. 1131 – 1147.<br />

ı ı EC-16 European Commission. <strong>Nuclear</strong> Illustrative Programme (PINC) presented under Article 40 of<br />

the European Treaty <strong>for</strong> the opinion of the European Economic and social Committee, COM(2016) 177<br />

final, 04/04/16. http://ec.europa.eu/transparency/regdoc/rep/1/2016/EN/<br />

1-2016-177-EN-F1-1.PDF, last visit: 23.05.2019<br />

Serial | Major Trends in Energy Policy and <strong>Nuclear</strong> <strong>Power</strong><br />

SMRs – Overview on <strong>International</strong> Developments and Safety Features ı Andreas Schaffrath and Sebastian Buchholz

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