This is NKS NKS-R NKS-B News Seminars NKS Reports Phantom Library

You are here: Homepage NKS-R Current activities BREDA_RPV

Current activities Call for proposals Travel assistance Previous activities  

BREDA_RPV


 

 Activity name  BREDA-RPV Barsebäck RPV trepan
 Project summary

Studies of mechanical and microstructural properties of Irradiated Low Alloy Steel

trepan samples from the Reactor pressure vessel wall of Barsebäck 2 (BREDA-RPV).

 

Irradiation induced ageing of the reactor pressure vessel (RPV) steel is closely

monitored in specified ageing management programs called surveillance programs.

These consist of a number of capsules positioned inside the RPV to allow for accelerated irradiation of the RPV material to predict the evolution of the mechanical

properties of the material as a function of neutron dose. The closed Barsebäck 2 reactor gives an opportunity to harvest samples from the aged reactor pressure vessel (RPV). The RPV was manufactured and welded with the same technique and high amounts of Nickel and Manganese as most Nordic RPVs. The weld material is now a limiting factor from a Long term operation, LTO, perspective as shown with studies at the PWR-plants Ringhals 3 and 4. By studying the evolution of the mechanical properties om both unirraidated samples and materials harvested from the reactor pressure vessel itself, it is possible to verify the validity of the surveillance specimen used for the monitoring of the RPV status. An example is if the (often separately performed) heat treatment of the surveillance samples gives representative values as compared to the real RPV. Another example is

the analysis of the degradation gradient through the depth of the RPV thickness due to irradiation, as the embrittlement properties at a ¼ of the wall thickness is used in the reporting to the radiation safety authority (SSM). A possibility to acquire for example three or four trepan samples from locations at different axial positions would make it possible to study the metallurgic variability and different ageing phenomena from thermal and radiation induced degradation: the core region has substantial neutron flux, while the RPV top lid has a substantial thermal component while the neutron flux is orders of magnitude lower. The study will be carried out as parts of as PhD studies performed at KTH, in strong collaboration with Chalmers on micro-structural analysis, and VTT for mechanical testing.

 Lead organisation  Royal Institute of Technology (KTH), Sweden
Contact person  Pål Efsing, efsing@kth.se, +46706254514

 


Contact NKS   NKS Sekretariatet
Boks 49
DK-4000 Roskilde
  Telephone +45 46 77 40 41
E-mail: nks@nks.org 
  Address for visitors
Directions and map
Website last modified: 25 April 2017