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110588

Stresses Induced by LOCA in Steam Generator Collector of VVER1000

Article

Last updated: 22 Jan 2023

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Abstract

During Double End Break Loss of Coolant Accident (DEBLOCA) in VVER1000 reactor, in the first second, pressure waves had been noticed in all points hitting the main components of the primary circuit. Studying the stresses due to DEBLOCA is important to avoid equipment failure. The main attention is focused on the pressure drops on the equipment, because this parameter determines the dynamic loads on the equipment, which can lead to its failure. ATHLET code is used to obtain pressure and temperature variation with time during the accident for the VVER1000 reactor Kalinin-3. The results are used in ANSYS Finite element package to calculate stresses in steam generator collector. The stress just before the emergency (at time 0.014 sec) was 4.3e7 pa and becomes 4.38e6 pa just after the emergency (at time =0.022 second). Fluctuations appear with two peaks of highest amplitude of 1.87e7 and 2.38e7 pa at time of 0.06 and 0.094 sec respectively which is well below the allowable stress. The results indicate safe operation of the equipment.

DOI

10.21608/ajnsa.2020.22763.1325

Keywords

VVER1000, LOCA, Steam Generator Collector, stresses

Authors

First Name

Azza

Last Name

Hassan

MiddleName

Ahmed

Affiliation

Safety of Nuclear Fuel Cycle Department, Egyptian Nuclear and Radiological Regulatory Authority,Cairo, Egypt

Email

azzaaea@yahoo.com

City

-

Orcid

-

First Name

Sergei

Last Name

Nikonov

MiddleName

Pavlovich

Affiliation

Department of Theoretical and Experimental Physics of Nuclear Reactors, National Research Nuclear University MEPHI, Moscow, Russia

Email

niks.ki@mail.ru

City

Moscow

Orcid

-

First Name

Dina

Last Name

Amer

MiddleName

Ali

Affiliation

Nuclear and Radiation Engineering Department, Faculty of Engineering, Alexandria University

Email

engineer_dinaali_2009@yahoo.com

City

Alexandria

Orcid

https://orcid.org/00

First Name

Khaled

Last Name

Ahmed

MiddleName

-

Affiliation

Safety of Nuclear Fuel Cycle Department, Egyptian Nuclear and Radiological Regulatory Authority, Cairo, Egypt

Email

atomeng@idsc.net.eg

City

Alexandria

Orcid

-

Volume

53

Article Issue

4

Related Issue

17672

Issue Date

2020-10-01

Receive Date

2020-02-03

Publish Date

2020-10-01

Page Start

13

Page End

20

Print ISSN

1110-0451

Online ISSN

2090-4258

Link

https://ajnsa.journals.ekb.eg/article_110588.html

Detail API

https://ajnsa.journals.ekb.eg/service?article_code=110588

Order

2

Type

Original Article

Type Code

455

Publication Type

Journal

Publication Title

Arab Journal of Nuclear Sciences and Applications

Publication Link

https://ajnsa.journals.ekb.eg/

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Article

Created At

22 Jan 2023