Published July 1990 | Version v1
Journal article

Experimental testing of life of screw joints for WWER type reactor pressure vessels

  • 1. Skoda, Plzen (Czechoslovakia). Zavod Energeticke Strojirenstvi
  • 2. Nauchno-Issledovatel'skij i Konstruktorskij Inst. Ehnergotekhniki, Moscow (USSR)
  • 3. Opytno-Konstruktorskoe Byuro Gidropress, Podol'sk (USSR)

Description

A series of life tests was performed on a model of the main screw joint at temperatures of 20 and 300 degC, and the performance of the joint was checked. The joint consists of M 140x6 bolts of 1800 mm in length, produced from steel 25Kh1MF or 38KhN3MFA. The maximum load (bend and tensile stress in combination) during a pressure test, 507 MPa, was at the point of contact of the bolt with the fixed flange. A special test device with a hydraulic force unit is described. The rack of the device consists of the bolt being tested, passing through the centre of the force unit. Force is transmitted to the joint via a nut simulating the fixed flange of the vessel. The test device allows tensile loading of the screw joint, repeated at a frequency of about 0.02 Hz. The maximum loading force is 8.3 MN. (M.D.). 5 figs., 1 tab., 4 refs

Additional details

Additional titles

Original title (Czech)
Experimentalni overeni zivotnosti sroubovych spoju pro tlakove nadoby reaktoru typu VVER

Publishing Information

Journal Title
Strojirenstvi
Journal Volume
40
Journal Issue
7
Series
Strojirenstvi.
Journal Page Range
412-416
ISSN
0039-2464
CODEN
STRJA

Optional Information

Notes
English translation available from Nuclear Information Center, 156 16 Prague 5-Zbraslav, Czechoslovakia, at US$ 10 per typewritten page.