Vergleichsanalysen zur Integrität von Reaktordruckbehältern vom Typ WWER-440

Jurgen Sievers; Heli Talja; X. Liu; A. Tutnov; Heikki Raiko

Vergleichsanalysen zur Integrität von Reaktordruckbehältern vom Typ WWER-440

Translated title of the contribution: Comparative analyses of the integrity of reactor pressure vessels, type WWER-440

Jurgen Sievers, Heli Talja, X. Liu, A. Tutnov, Heikki Raiko

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific

Abstract

Different FE models and programs were used to study the load of a RPV with an assumed partial circumferential crack in the near-core circumferential weld seam as a result of a mixing transient with temporal variation of coolant temperature in the axial and circumferential directions. Results tallied well with crack loads calculated by elasto-plastic FE analyses. Comparative calculations were performed involving simplified thermo-mechanical load assumptions, while assuming rotational-symmetric or strip-wise cooling at a RPV featuring assumed circumferential cracks of different depths and geometries.

Translated title of the contribution	Comparative analyses of the integrity of reactor pressure vessels, type WWER-440
Original language	German
Title of host publication	Sicherheit und Verfügbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik
Subtitle of host publication	Themenschwerpunkt: Komponentensicherheit
Place of Publication	Stuttgart
Publisher	Materials Testing Institute University of Stuttgart MPA
Number of pages	52
Publication status	Published - 1993
MoE publication type	B3 Non-refereed article in conference proceedings
Event	19. MPA-seminar Sicherheit und Verfügbarkeit in der Anlagentechnik - Stuttgart, Germany Duration: 7 Oct 1993 → 8 Oct 1993

Conference

Conference	19. MPA-seminar Sicherheit und Verfügbarkeit in der Anlagentechnik
Country/Territory	Germany
City	Stuttgart
Period	7/10/93 → 8/10/93

Cite this

@inproceedings{2e23ba05ba1f4307baaeca0ce9711c72,

title = "Vergleichsanalysen zur Integrit{\"a}t von Reaktordruckbeh{\"a}ltern vom Typ WWER-440",

abstract = "Different FE models and programs were used to study the load of a RPV with an assumed partial circumferential crack in the near-core circumferential weld seam as a result of a mixing transient with temporal variation of coolant temperature in the axial and circumferential directions. Results tallied well with crack loads calculated by elasto-plastic FE analyses. Comparative calculations were performed involving simplified thermo-mechanical load assumptions, while assuming rotational-symmetric or strip-wise cooling at a RPV featuring assumed circumferential cracks of different depths and geometries.",

author = "Jurgen Sievers and Heli Talja and X. Liu and A. Tutnov and Heikki Raiko",

note = "Project code: MET30191; 19. MPA-seminar Sicherheit und Verf{\"u}gbarkeit in der Anlagentechnik ; Conference date: 07-10-1993 Through 08-10-1993",

year = "1993",

language = "German",

booktitle = "Sicherheit und Verf{\"u}gbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik",

publisher = "Materials Testing Institute University of Stuttgart MPA",

address = "Germany",

}

Sievers, J, Talja, H, Liu, X, Tutnov, A & Raiko, H 1993, Vergleichsanalysen zur Integrität von Reaktordruckbehältern vom Typ WWER-440. in Sicherheit und Verfügbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik: Themenschwerpunkt: Komponentensicherheit. Materials Testing Institute University of Stuttgart MPA, Stuttgart, 19. MPA-seminar Sicherheit und Verfügbarkeit in der Anlagentechnik, Stuttgart, Baden-Württemberg, Germany, 7/10/93.

Vergleichsanalysen zur Integrität von Reaktordruckbehältern vom Typ WWER-440. / Sievers, Jurgen; Talja, Heli; Liu, X. et al.
Sicherheit und Verfügbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik: Themenschwerpunkt: Komponentensicherheit. Stuttgart: Materials Testing Institute University of Stuttgart MPA, 1993.

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific

TY - GEN

T1 - Vergleichsanalysen zur Integrität von Reaktordruckbehältern vom Typ WWER-440

AU - Sievers, Jurgen

AU - Talja, Heli

AU - Liu, X.

AU - Tutnov, A.

AU - Raiko, Heikki

N1 - Project code: MET30191

PY - 1993

Y1 - 1993

N2 - Different FE models and programs were used to study the load of a RPV with an assumed partial circumferential crack in the near-core circumferential weld seam as a result of a mixing transient with temporal variation of coolant temperature in the axial and circumferential directions. Results tallied well with crack loads calculated by elasto-plastic FE analyses. Comparative calculations were performed involving simplified thermo-mechanical load assumptions, while assuming rotational-symmetric or strip-wise cooling at a RPV featuring assumed circumferential cracks of different depths and geometries.

AB - Different FE models and programs were used to study the load of a RPV with an assumed partial circumferential crack in the near-core circumferential weld seam as a result of a mixing transient with temporal variation of coolant temperature in the axial and circumferential directions. Results tallied well with crack loads calculated by elasto-plastic FE analyses. Comparative calculations were performed involving simplified thermo-mechanical load assumptions, while assuming rotational-symmetric or strip-wise cooling at a RPV featuring assumed circumferential cracks of different depths and geometries.

M3 - Conference article in proceedings

BT - Sicherheit und Verfügbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik

PB - Materials Testing Institute University of Stuttgart MPA

CY - Stuttgart

T2 - 19. MPA-seminar Sicherheit und Verfügbarkeit in der Anlagentechnik

Y2 - 7 October 1993 through 8 October 1993

ER -

Vergleichsanalysen zur Integrität von Reaktordruckbehältern vom Typ WWER-440

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