In-vessel coolability and retention of a core melt
The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the risk oriented accident analysis methodology (ROAAM) and the assessment includes consideration of bounding scenarios and se...
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Published in | Nuclear engineering and design Vol. 169; no. 1; pp. 1 - 48 |
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Main Authors | , , , , , |
Format | Journal Article Conference Proceeding |
Language | English |
Published |
United States
Elsevier B.V
01.06.1997
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Subjects | |
Online Access | Get full text |
ISSN | 0029-5493 1872-759X |
DOI | 10.1016/S0029-5493(97)00009-5 |
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Abstract | The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the risk oriented accident analysis methodology (ROAAM) and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow for the delineation of the failure boundaries. The technical treatment in this assessment includes: (a) new data on energy flow from either volumetrically heated pools or non-heated layers on top, boiling and critical heat flux in inverted, curved geometries, emissivity of molten (superheated) samples of steel, and chemical reactivity proof tests; (b) a simple but accurate mathematical formulation that allows prediction of thermal loads by means of convenient hand calculations; (c) a detailed model programmed on the computer to sample input parameters over the uncertainty ranges, and to produce probability distributions of thermal loads and margins for departure from nucleate boiling at each angular position on the lower head; and (d) detailed structural evaluations that demonstrate that departure from nucleate boiling is a necessary and sufficient criterion for failure. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is ‘physically unreasonable’ Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. |
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AbstractList | The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the risk oriented accident analysis methodology (ROAAM) and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow for the delineation of the failure boundaries. The technical treatment in this assessment includes: (a) new data on energy flow from either volumetrically heated pools or non-heated layers on top, boiling and critical heat flux in inverted, curved geometries, emissivity of molten (superheated) samples of steel, and chemical reactivity proof tests; (b) a simple but accurate mathematical formulation that allows prediction of thermal loads by means of convenient hand calculations; (c) a detailed model programmed on the computer to sample input parameters over the uncertainty ranges, and to produce probability distributions of thermal loads and margins for departure from nucleate boiling at each angular position on the lower head; and (d) detailed structural evaluations that demonstrate that departure from nucleate boiling is a necessary and sufficient criterion for failure. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is ‘physically unreasonable’ Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the Risk Oriented Accident Analysis Methodology (ROAAM), and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow the delineation of the failure boundaries. The technical treatment in this assessment includes: (a) new data on energy flow from either volumetrically heated pools or non-heated layers on top, boiling and critical heat flux in inverted, curved geometries, emissivity of molten (superheated) samples of steel, and chemical reactivity proof tests, (b) a simple but accurate mathematical formulation that allows prediction of thermal loads by means of convenient hand calculations, (c) a detailed model programmed on the computer to sample input parameters over the uncertainty ranges, and to produce probability distributions of thermal loads and margins for departure from nucleate boiling at each angular position on the lower head, and (d) detailed structural evaluations that demonstrate that departure from nucleate boiling is a necessary and sufficient criterion for failure. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is {open_quotes}physically unreasonable.{close_quotes} Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. |
Author | Kymäläinen, O. Angelini, S. Theofanous, T.G. Salmassi, T. Liu, C. Additon, S. |
Author_xml | – sequence: 1 givenname: T.G. surname: Theofanous fullname: Theofanous, T.G. organization: Center for Risk Studies and Safety, University of California, Santa Barbara, CA 93106, USA – sequence: 2 givenname: C. surname: Liu fullname: Liu, C. organization: Center for Risk Studies and Safety, University of California, Santa Barbara, CA 93106, USA – sequence: 3 givenname: S. surname: Additon fullname: Additon, S. organization: Kaiser-Hill for DOE, P.O. Box 464, Golden, CO 80402, USA – sequence: 4 givenname: S. surname: Angelini fullname: Angelini, S. organization: Center for Risk Studies and Safety, University of California, Santa Barbara, CA 93106, USA – sequence: 5 givenname: O. surname: Kymäläinen fullname: Kymäläinen, O. organization: Nuclear Power Engineering, IVO International Ltd., FIN-01019 Ivo, Finland – sequence: 6 givenname: T. surname: Salmassi fullname: Salmassi, T. organization: Center for Risk Studies and Safety, University of California, Santa Barbara, CA 93106, USA |
BackLink | https://www.osti.gov/servlets/purl/467945$$D View this record in Osti.gov |
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Cites_doi | 10.1016/0029-5493(94)90108-2 10.1016/0029-5493(93)90260-G 10.1016/0029-5493(90)90003-G 10.1017/S0022112080002789 10.1016/0029-5493(94)90305-0 10.1002/aic.690260507 10.13182/NT89-A27694 10.1115/1.4008124 10.1016/0029-5493(96)01215-0 10.1016/0017-9310(75)90243-4 10.2172/10144034 10.1016/0029-5493(94)90120-1 10.1007/BF02557095 |
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Snippet | The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall... |
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SubjectTerms | COOLING CORIUM MELTDOWN NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS NUCLEAR REACTOR TECHNOLOGY PRESSURE VESSELS PWR TYPE REACTORS RETENTION RISK ASSESSMENT SAFETY ANALYSIS |
Title | In-vessel coolability and retention of a core melt |
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