Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock

Horst Kordisch, Heli Talja, Gunter Neubrech

Research output: Contribution to journalArticleScientificpeer-review

6 Citations (Scopus)

Abstract

In order to simulate a nuclear emergency cooling situation, longterm cooling tests (pressurized thermal shocks) were carried out under normal operating conditions on the reactor pressure vessel of the HDR (hot steam reactor). Naturally occuring circumferential cracks in the cylindrical part of the RPV, previously induced during cyclic thermal shock tests, were subjected to internal pressure and thermal stresses.
The aim of the test was crack initiation and a limited amount of stable crack growth.

Analyses, applying fracture mechanical assessment methods, were carried out before and after the test and these checked against the experimental results. To this end, comprehensive numerical analyses, investigations into material property characteristics, non-destructive and destructive (fractographical) tests were carried out. Due to the conservative assumptions, the results of the precalculation lay on the safe side; this was intended as these results served, among other aspects, as the basis for the experimental boundary condition.
The post calculation which was based on the actual crack geometry, the measured cooling medium temperature and the material properties local to the crack, was in good agreement with the experimental results.
Thus a tool is now available which can be successfully applied to the assessment of cracks in reactor components.
Original languageEnglish
Pages (from-to)171-192
JournalNuclear Engineering and Design
Volume124
Issue number1-2
DOIs
Publication statusPublished - 1990
MoE publication typeA1 Journal article-refereed

Fingerprint

remotely piloted vehicles
thermal shock
Thermal shock
crack
cracks
Cracks
reactors
Cooling
cooling
Materials properties
destructive tests
crack geometry
shock tests
pressure vessels
internal pressure
crack initiation
emergencies
Steam
thermal stresses
Pressure vessels

Cite this

Kordisch, Horst ; Talja, Heli ; Neubrech, Gunter. / Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock. In: Nuclear Engineering and Design. 1990 ; Vol. 124, No. 1-2. pp. 171-192.
@article{c2910b84f7994c5b8aeabd6a96c71aef,
title = "Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock",
abstract = "In order to simulate a nuclear emergency cooling situation, longterm cooling tests (pressurized thermal shocks) were carried out under normal operating conditions on the reactor pressure vessel of the HDR (hot steam reactor). Naturally occuring circumferential cracks in the cylindrical part of the RPV, previously induced during cyclic thermal shock tests, were subjected to internal pressure and thermal stresses. The aim of the test was crack initiation and a limited amount of stable crack growth.Analyses, applying fracture mechanical assessment methods, were carried out before and after the test and these checked against the experimental results. To this end, comprehensive numerical analyses, investigations into material property characteristics, non-destructive and destructive (fractographical) tests were carried out. Due to the conservative assumptions, the results of the precalculation lay on the safe side; this was intended as these results served, among other aspects, as the basis for the experimental boundary condition. The post calculation which was based on the actual crack geometry, the measured cooling medium temperature and the material properties local to the crack, was in good agreement with the experimental results. Thus a tool is now available which can be successfully applied to the assessment of cracks in reactor components.",
author = "Horst Kordisch and Heli Talja and Gunter Neubrech",
year = "1990",
doi = "10.1016/0029-5493(90)90363-3",
language = "English",
volume = "124",
pages = "171--192",
journal = "Nuclear Engineering and Design",
issn = "0029-5493",
publisher = "Elsevier",
number = "1-2",

}

Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock. / Kordisch, Horst; Talja, Heli; Neubrech, Gunter.

In: Nuclear Engineering and Design, Vol. 124, No. 1-2, 1990, p. 171-192.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock

AU - Kordisch, Horst

AU - Talja, Heli

AU - Neubrech, Gunter

PY - 1990

Y1 - 1990

N2 - In order to simulate a nuclear emergency cooling situation, longterm cooling tests (pressurized thermal shocks) were carried out under normal operating conditions on the reactor pressure vessel of the HDR (hot steam reactor). Naturally occuring circumferential cracks in the cylindrical part of the RPV, previously induced during cyclic thermal shock tests, were subjected to internal pressure and thermal stresses. The aim of the test was crack initiation and a limited amount of stable crack growth.Analyses, applying fracture mechanical assessment methods, were carried out before and after the test and these checked against the experimental results. To this end, comprehensive numerical analyses, investigations into material property characteristics, non-destructive and destructive (fractographical) tests were carried out. Due to the conservative assumptions, the results of the precalculation lay on the safe side; this was intended as these results served, among other aspects, as the basis for the experimental boundary condition. The post calculation which was based on the actual crack geometry, the measured cooling medium temperature and the material properties local to the crack, was in good agreement with the experimental results. Thus a tool is now available which can be successfully applied to the assessment of cracks in reactor components.

AB - In order to simulate a nuclear emergency cooling situation, longterm cooling tests (pressurized thermal shocks) were carried out under normal operating conditions on the reactor pressure vessel of the HDR (hot steam reactor). Naturally occuring circumferential cracks in the cylindrical part of the RPV, previously induced during cyclic thermal shock tests, were subjected to internal pressure and thermal stresses. The aim of the test was crack initiation and a limited amount of stable crack growth.Analyses, applying fracture mechanical assessment methods, were carried out before and after the test and these checked against the experimental results. To this end, comprehensive numerical analyses, investigations into material property characteristics, non-destructive and destructive (fractographical) tests were carried out. Due to the conservative assumptions, the results of the precalculation lay on the safe side; this was intended as these results served, among other aspects, as the basis for the experimental boundary condition. The post calculation which was based on the actual crack geometry, the measured cooling medium temperature and the material properties local to the crack, was in good agreement with the experimental results. Thus a tool is now available which can be successfully applied to the assessment of cracks in reactor components.

U2 - 10.1016/0029-5493(90)90363-3

DO - 10.1016/0029-5493(90)90363-3

M3 - Article

VL - 124

SP - 171

EP - 192

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

IS - 1-2

ER -