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Erschienen in:
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2014 | OriginalPaper | Buchkapitel

10. Assessment of Risk Studies and Severe Nuclear Accidents

verfasst von : Günter Kessler, Anke Veser

Erschienen in: The Risks of Nuclear Energy Technology

Verlag: Springer Berlin Heidelberg

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Abstract

In Chaps. 7 and 9 the results of the risk studies for LWRs and the facts and consequences of the severe nuclear accidents of Chernobyl and Fukushima were assessed. The severe nuclear accidents of Chernobyl and Fukushima resulted in contamination of large areas and in the evacuation of the population of large areas.
It is concluded that LWRs in Europe are built and operated in densely populated areas with cities of several 100,000 inhabitants. It is impossible to evacuate cities of that size in due time and their contamination is beyond anybody’s imagination. Therefore, the KHE safety concept was proposed around 1990 to build future LWRs such that the main accident path of the risk studies leading to the high number of deaths and to the large contamination of land should be eliminated by the safety design concept of the plant. The probabilistic safety studies leading to low frequencies of core melt in the range of 10−6 per year should be retained. However, the present risk concept should not be applicable any more to LWR plants built in future in Europe. It was concluded that the consequences of the most severe accidents in risk studies should be managed by the inner and outer containment of the reactor plant. A severe accident research program of the Research Center Karlsruhe, Germany, lasting for about two decades showed that it is possible to fulfill the requirements of the KHE concept. The KHE concept was essentially accepted by the German and French Safety Commissions and also incorporated in the German Atomic Law in 1994.
The main findings of the Karlsruhe research program for severe accidents were as follows:
  • A large scale steam explosion in the reactor pressure vessel of a PWR would not jeopardize the mechanical integrity of the reactor pressure vessel. Consequently a steam explosion followed by failure of the integrity of the reactor pressure vessel and of the containment as assumed in WASH-1400 and the German Risk study can be considered impossible.
  • A large scale hydrogen detonation after core melt in the spherical containment of a KWU PWR-1300 reactor plant cannot jeopardize the integrity of the steel containment. Nevertheless hydrogen recombiners in the containment are useful for preventing or mitigating some accident sequences.
  • Core melt down after a break of a pipe of the residual heat removal system in the annulus of the containment system or core melt down after an uncontrolled large scale steam generator tube break can be avoided by proper design.
  • Containment failure after core melt down under high primary coolant pressure, as assumed in WASH-1400 and the German risk study, can be avoided by manual or automatic opening of pressure relief valves (ADS systems of Chap. 3) or—as a limiting case—reinforced anchorage of the pressure vessel cover.
  • Core melting through the bottom part of the reactor pressure vessel can be counteracted by flooding the reactor pressure vessel on the outside with water (severe accident measure). Similar results can be obtained by installing a molten core spreading and cooling device (core catcher). Appropriate core catcher designs were developed after research.
  • A rising steam pressure in the inner containment after a core melt can be avoided by water spray systems.
  • A mechanically intact double containment, where the inner containment is either a steel containment or a concrete containment with an inner steel liner, having a leak rate of 0.3–1 % per day after a core melt accident and where the leaking radioactive gases and aerosols are passed from the annulus through aerosol filters to a stack can fulfill the requirements of the KHE safety concept. In this case the contamination by radioactive fission products is essentially limited to the site of the reactor plant. No evacuation of the population is necessary.
In summary all most severe accident consequences found in the WASH-1400 or the German risk study can be either controlled or eliminated or managed in future LWRs by appropriate design measures. Examples for such designs are EPR and KERENA (SWR-1000). Concluding remarks compare the KHE safety concept with the safety concept of presently operating reactors and more recent designs for LWRs.

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Vorheriges Kapitel The Severe Reactor Accidents of Three Mile Island, Chernobyl, and Fukushima
Nächstes Kapitel Introduction
Literatur
1.
2.
3.
4.
Samet JM et al (2013) Selected health consequences of the chernobyl disaster; a future systematic literature review, focus group findings, and future directions. http://​www.​greencross.​ch
5.
Hennies HH, Kessler G, Eibl J (1989) Improved containment concept for future pressurized water reactors. In: 5th International conference on emerging nuclear energy systems (ICENES), Karlsruhe, Germany, 3–6 July 1989
6.
Hennies HH, Kessler G, Eibl J (1992) Containments and core catchers in future reactors. Atomwirtschaft 37:238–247
7.
Eibl J et al (1992) How to eliminate containment failure in tomorrows PWRs (pressurized water reactors). Nucl Eng Int 37(453):51–55
8.
Kessler G (2002) Requirements for nuclear energy in the 21st century. Nuclear energy as a sustainable energy source. Prog Nucl Energy 60(3–4):309–325CrossRef
9.
(1975) Reactor safety study: an assessment of accidents risks in US Commercial Nuclear Power Plants. In: Rasmussen NC (ed) US Nuclear Regulatory Commission, WASH-1400 (NUREG-75/014), Washington
10.
Deutsche Risikostudie Kernkraftwerke Phase A (1980) Gesellschaft für Reaktorsicherheit (GRS). Verlag TÜV Rheinland
11.
Ehrhardt J et al (1982) Der Einsatz des Unfallfolgenmodells der “Deutschen Risikostudie Kernkraftwerke” bei Risikoabschätzungen zu verschiedenen Reaktortypen, KfK-Nachrichten, Jahrg. 14-4:269–277
12.
Bayer A, Heuser FW (1981) Basic aspects and results of the German Risk Study. Nucl Saf 22:695–709
13.
Erhardt J et al (1989) Radioactivity release and health consequences by filtered containment venting. In: SMIRT seminar: containment of nuclear reactors, Los Angeles, USA, 10–15 August 1989
14.
Qu J (1992) Konsequenzen und Wirksamkeit von Umsiedlungsmaß-nahmen nach kerntechnischen Unfällen, KfK 4990
15.
Gemeinsame Empfehlung von RSK und GPR für Sicherheitsanforderungen an zukünftige Kernkraftwerke mit Druckwasserreaktoren, Bundesanzeiger Nr. 218, 20. November 1993
16.
IPSN-GRS Proposals for the development of technical guidelines for future PWRs (1998) vol 5. Structuring GPR-RSK Recommendations as Guidelines, Common report IPSN/GRS No. 42. Institut de Protection et de Sureté Nucléaire, Saclay, France, Gesellschaft für Reaktorsicherheit, Garching, Germany
17.
Corradini ML et al (1988) Vapor explosion in light water reactors: a review of theory and modelling. Prog Nucl Energy 22:1–117CrossRef
18.
Magallon D (2005) FCI phenomena uncertainties impacting predictability of dynamic loading of reactor structures (from OECD SERENA programme). In: PSA-2 Workshop, Aix-en-Provence, 7–9 November 2005
19.
Berman M, Beck DF (1989) Steam explosion triggering and propagation: hypothesis and evidence. In: Proceedings of the 3rd international seminar on containment and nuclear reactors, UCLA, Los Angeles, 10–11 August 1989 (SNL report SAND89-1878C)
20.
21.
Consideration of BORAX-type reactivity accidents applied to research reactors. IRSH Report 2010/128. Institut de Radioprotection et de Sûreté Nucléaire, 08/2011
22.
Jacobs H et al (1994) Untersuchungen zur Dampfexplosion, PSF Statusbericht 23. März 1994 KfK 5326, Kernforschungszentrum Karlsruhe, 214–232
23.
Cronenberg AW, Benz R (1980) Vapour explosion phenomena with respect to nuclear reactor safety assessment. Adv Nucl Sci Technol 12:247–335CrossRef
24.
Fletcher DF, Anderson RP (1990) A review of pressure-induced propagation models of the vapour explosion process. Prog Nucl Energy 23:137–179CrossRef
25.
Board SJ et al (1975) Detonation of coolant explosions. Nature 254(3):319–321CrossRef
26.
Diab A et al (2000) Long-term validation of the molten fuel-moderator interactions model. Nucl Technol 169:114–125
27.
Kolev MI (1999) In-vessel melt water interaction caused by core support plate failure under molten pool. In: 7th International conference on nuclear engineering, Tokyo, Japan (ICONE 7360)
28.
29.
Struwe D et al (1999) Consequence evaluation of in-vessel fuel coolant interaction in the European Pressurized Water Reacto, FZKA 6316, Forschungszentrum Karlsruhe
30.
Allison M et al (1993) SCDAP/RELAP5 mod3.1 code manual, vol I–IV. NUREG/CR-6150, EGG-2720
31.
Coryell E et al (1997) SCDAP/RELAP5 mod3.2 code manual, vol I–V. NUREG/CR-6150, INEL-96/0422
32.
Summers RM et al (1995) MELCOR computer code manuals, vol 1–2 (Vers: 1.8.3). NUREG/CR-6119, SAND93-2185
33.
Valette M (1997) MC3D V3.0 directions for use. Commissariat a l’energie atomique Grenoble, STR/LTEM, STR-LTEM-96-52
34.
Berthoud G, Valette M (1994) Development of a multidimensional model for the premixing phase of a fuel coolant interaction. Nucl Eng Des 149:409–418CrossRef
35.
Jacobs H et al (1995) Multifield simulations of premixing experiments. In: Proceedings of “A multidisciplinary Intern. Seminar on intense multiphase interactions”, Santa Barbara, CA, USA, 9–13 June 1995, pp 56–69
36.
Krieg R (1995) Missiles caused by severe pressurized-water reactor accidents. Nucl Saf 36:299–309
37.
Krieg R et al (1995) Slug impact loading on the vessel head during a postulated in-vessel steam explosion in pressurized water reactors – assessments and discussion of the investigation strategy. Nucl Technol 111:369–385
38.
Hirt A (1998) Rechenmodell zum Aufprall von Kernschmelze auf die oberen Einbauten und den Deckel eines Reaktordruckbehälters, FZKA 6054, Forschungszentrum Karlsruhe
39.
Malmberg T (1995) Aspects of similitude theory in solid mechanics, Part I: Deformation behavior, FZKA 5657, Forschungszentrum Karlsruhe
40.
Krieg R et al (2003) Load carrying capacity of a reactor vessel under molten core slug impact. Final report including recent experimental findings. Nucl Eng Des 293:237–253CrossRef
41.
Stach T (1997) Zur Skalierung von Modellversuchen zum Aufprall flüssiger Massen auf deformierbare Strukturen, FZKA 5903, Forschungszentrum Karlsruhe
42.
Krieg R et al (1980) Transient, three-dimensional potential flow problems and dynamic response of the surrounding structures, Part I. Comput Phys 8(2):139CrossRefMathSciNet
43.
Krieg R et al (2000) Load carrying capacity of a reactor vessel head under a corium slug impact from a postulated in-vessel steam explosion. Nucl Eng Des 202:179–196CrossRef
44.
Krieg R (1997) Mechanical efficiency of the energy release during a steam explosion. Nucl Technol 117:151–157
45.
Theofanous B et al (1997) An assessment of steam explosion-induced containment failure, Part I: Probabilistic effects. Nucl Sci Eng 97:259–281
46.
Amarasooriya WH et al (1987) An assessment of steam-explosion-induced containment failure. Part III: Expansion and energy partition. Nucl Sci Eng 97:296–315
47.
Eibl J (1994) Zur bautechnischen Machbarkeit eines alternativen Con-tainments für Druckwasserreaktoren – Stufe 3, KfK 5366, Kernfor-schungszentrum Karlsruhe
48.
Travis JR et al (1998) GASFLOW-II: a three-dimensional-finite-volume fluid-dynamics code for calculating the transport, mixing, and combustion of flammable gases and aerosols in geometrically complex domains, theory and computational model, vol 1, FZKA-5994 and LA-13357-MS
49.
Redlinger R (1999) DET3D: a code for calculating detonations in reactor containments. Proc. Jahrestagung Kerntechnik 99, Kerntechnische Gesellschaft e.V. Deutsches Atomforum e.V. Annual Meeting on Nuclear Technology 99, Karlsruhe, 18.–20. Mai 1999
50.
Kotchourko AS et al (1999) Reactive flow simulations in complex 3D geometries using the COM3D code. Proc. Jahrestagung Kerntechnik 99, Kerntechnische Gesellschaft e.V. Deutsches Atomforum e.V. Annual Meeting on Nuclear Technology 99, Karlsruhe, 18.–20. Mai 1999
51.
Veser A et al (1999) Experiments on turbulent combustion and COM3D verification. Proc. Jahrestagung Kerntechnik 99, Kerntechnische Gesellschaft e.V. Deutsches Atomforum e.V. Annual Meeting on Nuclear Technology 99, Karlsruhe, 18.–20. Mai 1999
52.
Dorofeev SB et al (2001) Evaluation of limits for effective flame acceleration in hydrogen mixtures. J Loss Prev Process Indus 14:583–589CrossRef
53.
Dorofeev SB et al (1999) Effect of scale and mixture properties on behavior of turbulent flames in obstructed areas, FZKA 6268, Forschungszentrum Karlsruhe
54.
Kuznetsov M et al (1999) Effect of obstacle geometry on behaviour of turbulent flames, FZKA 6328, Forschungszentrum Karlsruhe
55.
Breitung W et al (2005) Innovative Methoden zur Analyse und Kontrolle des Wasserstoffverhaltens bei Kernschmelzunfällen, FZKA 7085, Forschungszentrum Karlsruhe
56.
Krieg R et al (2003) Assessment of the load-carrying capacities of a spherical pressurized water reactor steel containment under a postulated hydrogen detonation. Nucl Technol 141(2):109–121MathSciNet
57.
Rohde J et al (1997) Selection of representative accidents and evaluation of H2-control measures in PWR containments. In: 14th Session of RSK light water reactor safety committee, January 1997
58.
ABAQUS (1989) A general purpose linear and nonlinear finite element code, user manual standard 5.8. Hibbit, Karlson & Sorenson Inc., Providence, RI
59.
Bung H et al (1993) A new method for the treatment of impact and mechanics in reactor technology (SMIRT12), Stuttgart, Germany
60.
Krieg R (2005) Failure strains and proposed limit strains for a reactor pressure vessel under severe accident conditions. Nucl Eng Des 235:199–212CrossRef
61.
Jeschke J et al (2011) Critical strains and melting phenomena for different steel sheet specimens under uniaxial loading. Nucl Eng Des 241:2045–2052CrossRef
62.
Ostermann D et al (2011) Critical strains and necking phenomena for different steel specimens under biaxial loading. Nucl Eng Des 241:2045–2052CrossRef
63.
Breitung W et al (2005) Innovative Methoden zur Analyse und Kontrolle des Wasserstoffverhaltens bei Kernschmelzunfällen, Abschlußbericht zu Teilprojekt 1 des HGF-Strategiefondsprojekts 98/07
64.
Deutsche Risikostudie Kernkraftwerke Phase B (1990) Verlag TÜV Rheinland, Köln
65.
Smidt D (1979) Reaktorsicherheitstechnik, Sicherheitssysteme und Stör-fallanalyse für Leichtwasserreaktoren und Schnelle Brüter. Springer, Berlin
66.
Jacobs G (1995) Dynamic loads from reactor pressure vessel core melt through under high primary pressure. Nucl Technol 111:351–356
67.
68.
Czech J et al (1999) European pressurized water reactor: safety objectives and principles. Nucl Eng Des 187:25–32CrossRef
69.
Tong LS (1968) Core cooling in a hypothetical loss of cooling accident. Estimate of heat transfer in core meltdown. Nucl Eng Des 8:309–312CrossRef
70.
Henry RE et al (1993) External cooling of a reactor vessel under severe accident conditions. Nucl Eng Des 139:31–43CrossRef
71.
Rempe JL et al (1993) Light water reactor lower head failure. Idaho National Engineering Laboratory, NUREG/CR-5642, EGG-2618
72.
Thinnes GL et al (1989) Comparison of thermal and mechanical responses of the Three Mile Island Unit 2 vessel. Nucl Technol 87:1036–1049
73.
Cummings WE et al (2013) Westinghouse AP1000 advanced passive plant. In: Proceedings of ICAPP 2003, Paper 3235, Cordoba, Spain
74.
Park JW (2012) Investigation of core melt coolability inside the large evolutionary advanced power reactor APR1400, atw 57, Heft 1
75.
Stosic ZV et al (2008) Boiling water reactor with innovative safety concept: the generation III+ SWR-1000. Nucl Eng Des 238:1863–1901CrossRef
76.
Ma W et al (2009) On the effectiveness of CRGT cooling as a severe accident management measure for BWRs. In: OECD workshop on the implementation of severe accident management measures (SAMI-2009), Schloß Böttstein, Switzerland
77.
Kolev NI (2004) External cooling – the SWR-1000 severe accident management strategy. In: 12th International conference on nuclear engineering – ICONE-12, Arlington, VA, USA, 25–29 April
78.
Kuczera B (1991) Aktueller Stand der Reaktorsicherheitsforschung dargestellt anhand von Ergebnissen aus der deutschen Risikostudie Kernkraftwerke – Phase B, Radioaktivität – Risiko – Sicherheit, Herausgeber Kernforschungszentrum Karlsruhe (2. veränderte und aktualisierte Auflage 1991)
79.
Reimann M (1987) Verification of the WECHSL-code on melt/concrete interaction and application to the core melt accident. Nucl Eng Des 103:127–137CrossRef
80.
Reimann M et al (1981) The WECHSL-Code: a computer program for the interaction of a core melt with concrete, KfK 2980, Kernforschungszentrum Karlsruhe
81.
Krieg R et al (1987) Failure pressure and failure mode of the latest type of German PWR containments. Nucl Eng Des 104:381–390CrossRef
82.
Göller B et al (1988) Failure pressure and failure mode of the bolted connection for the large component port in German PWR containments. Nucl Eng Des 106:35–45CrossRef
83.
Birkhofer A (1989) Anlageninterner Notfallschutz, Achtes deutsches Atomrechtssymposium 1.–3. März 1989 München, Carl Heymann Verlag KG, Köln
84.
Schenk H (1990) Maßnahmen zum anlageninternen Notfallschutz. Atomwirtschaft 11:514–520
85.
Kessler G et al (1995) Confinement of the radiological source term during beyond-design-basis events in future pressurized water reactors. Nucl Technol 111:305–318
86.
87.
Tromm W et al (1991) Radionuclide dispersion after core-concrete melt leaching by groundwater. Kerntechnik 56(6):7–12
88.
Al-Omari I (1990) Abschätzung der Strahlenexposition infolge störfallbe-dingter Radionuklideinleitungen von kerntechnischen Anlagen in Fließge-wässer unter Berücksichtigung der Zeitabhängigkeit relevanter Parameter, KfK 479
89.
Alsmeyer H et al (1987) BETA-experiments in verification of the WECHSL-code: experimental results on the melt-concrete interaction. Nucl Eng Des 103:115–125CrossRef
90.
Alsmeyer H (1989) Containment loadings from melt-concrete interaction. Nucl Eng Des 117:45–50CrossRef
91.
Turricchia A (1992) How to avoid molten core/concrete interaction (and steam explosions). In: Proceedings of the 2nd OECD(NEA) CSNI Spec. meeting on molten core debris-concrete interaction, KfK 5108, NEA/CSNI/R(92)10, Ed. H. Alsmeyer, p 503
92.
Seiler JM et al (1992) Conceptual studies of core catchers for advanced LWRs. In: Proceedings of the international conference design and safety of advanced nuclear power plants, Tokyo, October 1992, vol III, p 23.3-1
93.
Alsmeyer H et al (1998) Beherrschung und Kühlung von Kernschmelzen außerhalb des Druckbehälters. Nachrichten Forschungszentrum Karlsruhe. Jahrg 29(4):327–335
94.
Tromm W et al (1993) Fragmentation of melts by water inlet from below. In: 6th International topical meeting on nuclear reactor thermal hydraulics (NURETH-6), Grenoble, 5–8 October 1993
95.
Fieg G et al (1996) Simulation experiments on the spreading behavior of molten core melts. In: Proceedings of the 1996 national heat transfer conference, Houston, TX, 3–6 August 1996. American Nuclear Society, La Grange Park, IL, vol 9:121–130
96.
Lewis BJ (2008) Overview of experimental programs on core melt progression and fission product release behaviour. J Nucl Mater 380:126–143CrossRef
97.
Meyer L et al (2003) Low pressure corium dispersion experiments with simulant fluids in a scaled annular cavity. Nucl Technol 141:257–274
98.
Meyer L et al (2009) Direct containment heating integral effects tests in geometries of European nuclear power plants. Nucl Eng Des 239:2070–2084CrossRef
99.
Köberlein K (2001) Bewertung des Unfallrisikos fortschrittlicher DWR in Deutschland. GRS-175, Gesellschaft für Reaktorsicherheit
100.
Bundesgesetzblatt, Gesetz zur Sicherung des Einsatzes von Steinkohle in der Verstromung und zur Änderung des Atomgesetzes und des Stromeinspeisungsgesetzes (Artikel 4, 7. Gesetz zur Änderung des Atomgesetzes, § 7 Absatz 2a), Nr. 46, 19.7.1994
101.
American Nuclear Society, Fukushima Daiichi: ANS Comittee Report, revised June 2012
102.
Kersting E et al (1993) Safety analysis for boiling water reactors. A summary, GRS-98. Gesellschaft für Anlagen- und Reaktorsicherheit, Garching
103.
Nazaré S et al (1975) Über theoretische und experimentelle Möglichkeiten zur Bestimmung der Stoffwerte von Corium, Abschlußbericht Teil II, KFK 2217
104.
Schneider H et al (1975) Zur Bestimmung der Zusammensetzung ver-schiedener Corium-Schmelzen, KFK 2227
105.
Sehgal B (2012) Nuclear safety in light water reactors, severe accident phenomenology. Elsevier, Academic Press, Waltham, USA
Metadaten
Titel
Assessment of Risk Studies and Severe Nuclear Accidents
verfasst von
Günter Kessler
Anke Veser
Copyright-Jahr
2014
Verlag
Springer Berlin Heidelberg
Buch
The Risks of Nuclear Energy Technology

Print ISBN: 978-3-642-55115-4

Electronic ISBN: 978-3-642-55116-1

Copyright-Jahr: 2014

DOI
https://doi.org/10.1007/978-3-642-55116-1_10