External Events Importance for Safety of the Ignalina Nuclear Power Plant

2008 ◽  
Author(s):  
Kristina Kupciuniene ◽  
Robertas Alzbutas
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Forest Fires ◽  
Nuclear Power ◽  
Statistical Data ◽  
Initial Conditions ◽  
Analytical Formula ◽  
Estimation Model ◽  
External Events ◽  
Aircraft Crash

Probabilistic risk analysis of external events impact on the safety important systems of Ignalina nuclear power plant (NPP) is performed. At first, the methodology was established for screening out external events, which impact on Ignalina NPP safety is not significant. In order to estimate probabilities of external events occurrences the statistical data were collected, mathematical models were constructed and probabilities of these events occurrences were determined. For risk estimation, the following external events were studied: forest fires, external floods, aircraft crash, seismic events, extreme winds, fall of frequency in electricity network and loss of an external electricity supply. The aircraft crash event was modeled and analyzed in more detail. The crash probability estimation model is improved considering uncertain data. The aircraft crash probability on the territory of the Ignalina NPP with the radius r is expressed by the derived analytical formula. This formula is used to calculate the aircraft crash probability applying the most recent statistical data. The aircraft crash dependencies upon the amount of flights and crashes in the different radius territories were analyzed. Relationship of non-flying zone around Ignalina NPP and aircraft crash frequency was investigated. As a part of the initial conditions and parameters of aircraft crash model are not well-known or have different values for various types of aircrafts, the sensitivity analysis was performed for the model. This analysis determines the parameters that have the greatest influence on the model results. Conclusions about the importance of the parameters and sensitivity of the results are obtained using a sensitivity measures of the model under analysis.

Numerical analysis of nuclear power plant structure subjected to aircraft crash

2017 ◽  
Vol 9 (4) ◽  
pp. 341-352 ◽  
Author(s):  
Reza Saberi ◽  
Majid Alinejad ◽  
Mir Omid Mahdavi ◽  
Kamran Sepanloo
Keyword(s):  
Numerical Analysis ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Plant Structure ◽  
Aircraft Crash

Integrated probabilistic analysis of nuclear power plant building damage due to an aircraft crash

2011 ◽  
Vol 16 (1) ◽  
pp. 49-62 ◽  
Author(s):  
Gintautas Dundulis ◽  
Ronald F. Kulak ◽  
Robertas Alzbutas ◽  
Eugenijus Uspuras
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Probabilistic Analysis ◽  
Nuclear Power ◽  
Building Damage ◽  
Aircraft Crash

Design of Severe Accident Management Systems for Beyond Design Basis External Hazards at Paks NPP

2016 ◽  
Author(s):  
Tamás János Katona ◽  
András Vilimi
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Severe Accident ◽  
Management Systems ◽  
Basic Question ◽  
Severe Accidents ◽  
Design Basis ◽  
Accident Management ◽  
External Events

Paks Nuclear Power Plant identified the post-Fukushima actions for mitigation and management of severe accidents caused by external events that include updating of some hazard assessments, evaluation of capacity / margins of existing severe accident management facilities, and construction of some mew systems and facilities. In all cases, the basic question was, what level of margin has to be ensured above design basis external hazard effects, and what level of or hazard has to be taken for the design. Paks Nuclear Power Plant developed certain an applicable in the practice concept for the qualification of already implemented and design the new post-Fukushima measures that is outlined in the paper. The concept and practice is presented on several examples.

Aircraft crash upon outer containment of nuclear power plant

1996 ◽  
Vol 160 (1-2) ◽  
pp. 13-50 ◽  
Author(s):  
H. Abbas ◽  
D.K. Paul ◽  
P.N. Godbole ◽  
G.C. Nayak
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Aircraft Crash

scholarly journals Kouno Fumiyo's Hi no tori ('Bird of the Sun') series as documentary manga: Memory and 3.11

2019 ◽  
Vol 12 (3) ◽  
pp. 163-177
Author(s):  
Linda Flores
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Statistical Data ◽  
Great East Japan Earthquake ◽  
Prose Poetry ◽  
The Sun ◽  
Critical Spaces ◽  
Fukushima Daiichi ◽  
Presence And Absence

Abstract Fumiyo Kouno's two-part manga series Hi no tori (2014) and Hi no tori 2 (2016) documents the story of a cockerel's search for his missing wife in the months and years following '3.11', the Triple Disaster of 11 March 2011, consisting of the Great East Japan Earthquake, tsunami and nuclear meltdown at Fukushima Daiichi Nuclear Power Plant. Both Hi no tori and Hi no tori 2 possess an unusual layout; they are comprised of various elements, including drawings, prose, poetry, statistical data, maps and commentary by the artist. This article argues that in its unique presentation of visual and textual elements, the Hi no tori series employs the medium of documentary comics to negotiate the complex critical spaces in between fiction and nonfiction, past and present, presence and absence, visibility and invisibility and, importantly, between forgetting or the fading of memories (fūka) and reconstruction (fukkō). It examines the Hi no tori series as an adaptation within the medium of comics towards a more accurate and ethical representation of 3.11 and its aftermath.

Kalman Filter Based Predictive Trip Detection for Nuclear Power Plant Safety Systems

2014 ◽  
Author(s):  
Drew J. Rankin ◽  
Jin Jiang
Keyword(s):  
Kalman Filter ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Estimation Model ◽  
Response Characteristics ◽  
Plant Safety ◽  
Error Covariance ◽  
Nuclear Power Plant Safety ◽  
Safety Systems

The primary aim of this work is to utilize a Kalman filter (KF) to predict reaching the trip set-point for a trip parameter in a nuclear power plant (NPP). To address uncertainty in the predicted measurements, prediction bounds are calculated by propagating the state error covariance. These predicted bounds enable the calculation of levels of confidence in making trip decisions. Further, to address uncertainty in the estimation model, the observed prediction error is used to offset the predicted measurements. The predictive trip detection routines are evaluated through simulations of a single NPP sub-system. More specifically, the water level parameter in a steam generator of a NPP is considered. The model of this sub-system is represented by the Irving linear parameter varying (LPV) model with inverse response characteristics. The simulations include a level low postulated initiating event (PIE) made to occur during two different common power transients for various estimation models. The results of this paper are a proof of concept for KF-based predictive trip detection which is demonstrated to achieve reduced time-to-trip when applied to a single sub-system.

Sign in / Sign up

Export Citation Format

Share Document