Results 261 to 270 of about 423,593 (300)

In-vessel retention of corium at the Loviisa plant

Nuclear Engineering and Design, 1997
In-vessel retention of corium has been approved to be part of the severe accident management strategy for IVO's Loviisa plant. The approach selected takes advantage of the unique features of the plant such as a low power density, a reactor pressure vessel (RPV) without penetrations at the bottom, and ice-condenser containment which ensures a flooded ...
O. Kymäläinen, H. Tuomisto, T.G. Theofanous   +2 more
openaire   +1 more source

Analysis of feasibility of a new core catcher for the in-vessel core melt retention strategy [PDF]

Progress in Nuclear Energy, 2020
This study deals with the feasibility study of a new in-vessel core melt retention (IVCMR) strategy capable to extend the coping period in the event of adverse situations, involving the melting of the core.
Rosa Lo Frano, Riccardo Ciolini, Alessio Pesetti   +2 more
exaly   +2 more sources

Consequences of material effects on in-vessel retention

Nuclear Engineering and Design, 2007
Abstract In-vessel retention (IVR) consists in cooling the corium contained in the reactor vessel by natural convection and reactor cavity flooding. This strategy of severe accident management enables the corium to be kept inside the second confinement barrier: the reactor vessel.
Jean Marie Seiler, Bruno Tourniaire, Françoise Defoort, Karine Froment   +3 more
openaire   +1 more source

In-vessel retention analysis for a typical PHWR

Life Cycle Reliability and Safety Engineering, 2017
A very unlikely sequence of events with multiple failures of safety systems and human actions may lead to severe accidents like simultaneous occurrence of loss of coolant accident $$\left( \text {LOCA} \right)$$
Anuj Kumar Deo, P. K. Baburajan, R. Srinivasa Rao, U. K. Paul, Avinash J. Gaikwad   +4 more
openaire   +1 more source

In-Vessel Tritium Retention and Removal in ITER-FEAT

Physica Scripta, 2001
Erosion of the divertor and first-wall plasma-facing components, tritium uptake in the re-deposited films, and direct implantation in the armour material surfaces surrounding the plasma, represent crucial physical issues that affect the design of future fusion devices.
G. Federici, J. N. Brooks, M. Iseli, C. H. Wu   +3 more
openaire   +1 more source

In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

Journal of Nuclear Engineering and Radiation Science, 2019
Abstract In pressurized heavy water reactors (PHWRs), multiple failures of engineered safety features may cause a failure of core cooling eventually leading to core collapse. The failed fuel and fuel channels relocate to the bottom of the calandria vessel (CV) and form a terminal debris bed, which generates decay heat.
Sumit V. Prasad, P. P. Kulkarni, D. C. Yadav, P. K. Verma, A. K. Nayak   +4 more
openaire   +1 more source

Challenges left in the area of in-vessel melt retention

Nuclear Engineering and Design, 2001
The in-vessel melt retention becomes an important safety objective for the present or future middle power nuclear plants, so care has to be taken in the evaluation of the various phenomena related to ensuring the feasibility of this objective. Since the prediction of the relevant phenomena has to be performed for the prototypical accident conditions ...
V. Asmolov, N.N. Ponomarev-Stepnoy, V. Strizhov, B.R. Sehgal   +3 more
openaire   +1 more source

Analysis of safety margin of in-vessel retention for AP1000

Nuclear Engineering and Design, 2010
In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by most operating nuclear power plants and advanced light water reactors (ALWRs), AP600, AP1000, etc. External reactor vessel cooling (ERVC) is a novel severe accident management for IVR analysis.
Y.P. Zhang, S.Z. Qiu, G.H. Su, W.X. Tian
openaire   +1 more source

Influence of crust formation on the heat load to a reactor vessel under an in-vessel retention condition

Annals of Nuclear Energy, 2022
Abstract The heat load imposed on a reactor vessel was measured with and without the crust layer under an IVR-ERVC condition. Mass transfer experiments were performed based on heat and mass transfer analogy to achieve high RaʹH of order 1015 with compact test rigs.
Joon-Soo Park, Hae-Kyun Park, Bum-Jin Chung   +2 more
openaire   +1 more source

Heat load imposed on reactor vessels during in-vessel retention of core melts

Nuclear Engineering and Design, 2016
Abstract We measured the heat load imposed on reactor vessels by natural convection of the oxide pool in severe accidents. Based on the analogy between heat and mass transfer, mass transfer experiments were performed using a copper sulfate electroplating system.
Su-Hyeon Kim, Bum-Jin Chung
openaire   +1 more source