ICONE11-36102 Core Catcher for Tianwan NPP with VVER-1000 reactor. Concept, Design and Justification

Svetlov, S. V.; Bezlepkin, V. V.; Kukhtevich, I. V.; Bechta, Sevostian; Granovsky, V.S.; Khabensky, V.B.; Asmolov, V. G.; Proklov, V. B.; Sidorov, A. S.; Nedorezov, A. B.; Strizhov, V. F.; Гусаров, В. В.; Udalov, Yu. P.

doi:10.1299/jsmeicone.2003.104

Cited by 4 publications

(3 citation statements)

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“…The ex-vessel corium retention is an alternative approach to localize and stabilize the corium. This approach is based either on corium retention in core catcher located in reactor pit below the reactor vessel (e.g., VVER-1000 design) [28] or corium retention in special spreading compartment located under the reactor vessel (e.g., EPR). However, preventing the spreading/dispersion of such large amounts of radioactive material appears to be more attractive in order to avoid very long and very expensive postaccident decontamination tasks.…”

Section: Severe Accident Management Strategiesmentioning

confidence: 99%

A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

Bachrata

Bertrand

Marie

et al. 2020

Journal of Nuclear Engineering and Radiation Science

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The nuclear safety approach has to cover accident sequences involving core degradation in order to develop reliable mitigation strategies for both existing and future reactors. In particular, the long-term stabilization of the degraded core materials and their coolability has to be ensured after a severe accident. This paper focuses on severe accident phenomena in Pressurized Water Reactors (PWR) compared to those potentially occurring in future GenIV-type Sodium Fast Reactors (SFR). Firstly, the two considered reactor concepts are introduced by focusing on safety aspects. The severe accident scenarios leading to core melting are presented and the initiating events are highlighted. The paper focuses on in-vessel severe accident phenomena, including the chronology of core damage, major changes in the core configuration and molten core progression. Regarding the mitigation means, the in-vessel retention phenomena and the core catcher characteristics are reviewed for these different nuclear generation concepts (II, III and IV). A comparison between the PWR and SFR severe accident evolution is provided as well as the relation between governing physical parameters and the adopted mitigation provisions for each reactor concept. Finally, it is highlighted how the robustness of the safety demonstration is established by means of a combined probabilistic and deterministic approach.

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Section: Severe Accident Management Strategiesmentioning

confidence: 99%

A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

Bachrata

Bertrand

Marie

et al. 2020

Journal of Nuclear Engineering and Radiation Science

View full text Add to dashboard Cite

show abstract

“…The latest design of VVER-1000 reactors includes a unique core catcher system under the reactor vessel for the reception, localization, and cool-down of the molten corium in the course of severe accidents [84]. …”

Section: In-vessel Melt Retentionmentioning

confidence: 99%

In-Vessel Core Degradation

2012

Nuclear Safety in Light Water Reactors

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“…It is the basis of the EPR core catcher concept [42] [43]. Spreading is also important for the discharge of corium in large reactor pits and in core-catchers such as that of the Tian Wan VVER-1000 [44]. Afterward, the gate opens, and the corium melt is released into a spreading compartment.…”

Section: Introductionmentioning

confidence: 99%

Late Containment Failure

2012

Nuclear Safety in Light Water Reactors

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ICONE11-36102 Core Catcher for Tianwan NPP with VVER-1000 reactor. Concept, Design and Justification

Cited by 4 publications

References 0 publications

A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

In-Vessel Core Degradation

Late Containment Failure

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