TY - GEN
T1 - Thermal-mechanical fatigue analysis of a main steam isolation valve of a boiling water reactor-5
AU - Álvarez-Loya, I.
AU - Santillán-Gómez, J. A.
AU - Huesca-Damián, C. J.
AU - Hernández Gómez, L. H.
AU - Beltrán-Fernández, J. A.
AU - Ruiz-López, P.
N1 - Publisher Copyright:
© Springer Nature Singapore Pte Ltd. 2019.
PY - 2019
Y1 - 2019
N2 - The Nuclear Steam Supply System (NSSS) of a Boiling Water Reactor (BWR) has been designed for directing and controlling the steam flow, from the reactor pressure vessel to the turbine. Furthermore, this system provides over-pressure protection for the Reactor Coolant System (RCS) and prevents fuel damage by restricting the loss of coolant in the reactor. In this paper, the fatigue and aging of a generic Main Steam Isolation Valve (MSIV) was analyzed. The body of such valve was evaluated. These conditions affect adversely the capacity and the functions of the valve. In the case, there is the risk of uncontrolled releases of radioactive particles to the external environment. The thermal fatigue analysis, which is reported, included three main thermal transients. They affect the NSSS system during its operating life. They are test of valve, shutdown of plant and turbine stop valve closure (TSV). All these evaluations were developed with a 3D CAD model in conjunction with the Finite Element Method. Finally, the remaining life and the allowable fatigue cycles were determined before the failure takes place. This work was based on the guidelines applicable to Nuclear Power Plants (NPP´s) contained in the ASME code.
AB - The Nuclear Steam Supply System (NSSS) of a Boiling Water Reactor (BWR) has been designed for directing and controlling the steam flow, from the reactor pressure vessel to the turbine. Furthermore, this system provides over-pressure protection for the Reactor Coolant System (RCS) and prevents fuel damage by restricting the loss of coolant in the reactor. In this paper, the fatigue and aging of a generic Main Steam Isolation Valve (MSIV) was analyzed. The body of such valve was evaluated. These conditions affect adversely the capacity and the functions of the valve. In the case, there is the risk of uncontrolled releases of radioactive particles to the external environment. The thermal fatigue analysis, which is reported, included three main thermal transients. They affect the NSSS system during its operating life. They are test of valve, shutdown of plant and turbine stop valve closure (TSV). All these evaluations were developed with a 3D CAD model in conjunction with the Finite Element Method. Finally, the remaining life and the allowable fatigue cycles were determined before the failure takes place. This work was based on the guidelines applicable to Nuclear Power Plants (NPP´s) contained in the ASME code.
KW - Aging
KW - Cumulative Usage Factor
KW - Damage
KW - Nuclear Power Plant
KW - Thermal transient stress
UR - http://www.scopus.com/inward/record.url?scp=85068413866&partnerID=8YFLogxK
U2 - 10.1007/978-981-13-0411-8_34
DO - 10.1007/978-981-13-0411-8_34
M3 - Contribución a la conferencia
SN - 9789811304101
T3 - Lecture Notes in Mechanical Engineering
SP - 379
EP - 389
BT - Proceedings of the 7th International Conference on Fracture Fatigue and Wear, FFW 2018
A2 - Abdel Wahab, Magd
PB - Pleiades journals
T2 - 7th International Conference on Fracture Fatigue and Wear, FFW 2018
Y2 - 9 July 2018 through 10 July 2018
ER -