TY - GEN
T1 - An approach for evaluating the consequence of cyber attacks on nuclear power plants
AU - Varuttamaseni, Athi
AU - Bari, Robert
AU - Youngblood, Robert
N1 - Publisher Copyright:
© 2017 by American Nuclear Society. All rights reserved.
PY - 2017
Y1 - 2017
N2 - Evaluating the effectiveness of cybersecurity measures implemented at a nuclear power plant requires an understanding of the types of attack that are possible and the consequences of those attacks. In this paper, a systematic approach to determining the system response to various cyber attack scenarios is described. Starting from the initial attack vector, the chain of events taking the plant from the initial state to a compromised state is constructed based on the type of components in the system and the method of attack. System response is evaluated using the standard thermal-hydraulics model of the plant. The paper demonstrates the approach by analyzing the low pressurizer pressure trip function of the reactor protection system and shows how an attack against plant network infrastructure can lead to a noticeable impact on the peak clad temperature following a small loss of coolant accident.
AB - Evaluating the effectiveness of cybersecurity measures implemented at a nuclear power plant requires an understanding of the types of attack that are possible and the consequences of those attacks. In this paper, a systematic approach to determining the system response to various cyber attack scenarios is described. Starting from the initial attack vector, the chain of events taking the plant from the initial state to a compromised state is constructed based on the type of components in the system and the method of attack. System response is evaluated using the standard thermal-hydraulics model of the plant. The paper demonstrates the approach by analyzing the low pressurizer pressure trip function of the reactor protection system and shows how an attack against plant network infrastructure can lead to a noticeable impact on the peak clad temperature following a small loss of coolant accident.
UR - https://www.scopus.com/pages/publications/85047815341
M3 - Conference contribution
AN - SCOPUS:85047815341
T3 - International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017
SP - 1199
EP - 1204
BT - International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017
PB - American Nuclear Society
T2 - 2017 International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017
Y2 - 24 September 2017 through 28 September 2017
ER -