Materials Research Lab (LBM)
Contact Data
Lab Acting Head
DSc. Eng. Łukasz Kurpaska, prof. NCBJ
e-mail: lukasz.kurpaska@ncbj.gov.pl
Head of the laboratory for Structural, Corrosion and Chemical Research
DSc. Eng. Jarosław Jasiński, prof. NCBJ
e-mail: jaroslaw.jasinski@ncbj.gov.pl
Head of the Non-destructive Testing Laboratory
MSc. Eng. Marcin Kowal
e-mail: marcin.kowal@ncbj.gov.pl
Mechanical Research Laboratory
PhD. Eng. Małgorzata Frelek-Kozak
e-mail: malgorzata.frelek@ncbj.gov.pl
LBM Secretariat
Elżbieta Szulim
e-mail: elzbieta.szulim@ncbj.gov.pl tel. (22) 273 10 62
Basic information
The Materials Research Laboratory (LBM) of the National Centre for Nuclear Research is located at the Research Centre in Świerk, approximately 5 km north-east of Otwock and 30 km south-east of Warsaw. LBM conducts research, re-approval and diagnostic works on construction materials and their welded joints in the field of widely understood materials science, using destructive and non-destructive methods. Non-irradiated and irradiated materials are tested.
LBM includes the Laboratory for Structural, Corrosion and Chemical Testing, the Laboratory of Mechanical Testing, the Laboratory of Non-Destructive Testing and the Work of Hot Chambers consisting of a set of 12 lead chambers with a maximum shielding of 100 Ci (3.7 × 1012 Bq), equipped with appropriate technological installations and connected to each other by a transport tunnel. The chambers are equipped with equipment for testing the properties of irradiated construction materials.
For over thirty years, LBM has been accredited by the Polish Centre for Accreditation (PCA) as an accredited research laboratory (AB 025). The Polish Centre for Accreditation is a signatory of multilateral agreements within international organizations operating in the field of accreditation, i. e. EA MLA, IAF MLA and ILAC MRA. For this reason, the results of accredited activities, included in the test reports issued by LBM, bear the ILAC MRA label in addition to the PCA accreditation mark, and thus are recognized and recognized abroad.
The Material Testing Laboratory offers research services to commercial entities and scientific partners. We provide our clients with independent, impartial and reliable performance of tests thanks to the implemented management system, in accordance with the declared Quality Policy and the requirements of the PN-EN ISO / IEC 17025: 2018–02 standard. The laboratory maintains traceability in accordance with the requirements of the relevant own procedures and the requirements of the Polish Centre for Accreditation.
The employees of the Material Research Laboratory participate in national and international research projects financed by the National Science Centre, the National Centre for Research and Development, the Foundation for Polish Science, H2020 instruments or the French Embassy in Poland. Research conducted by LBM employees focuses on the assessment of the impact of radiation defects in new materials such as: ODS steels, nickel and zirconium alloys, martensitic-ferritic steels, Al2O3 coatings and graphite. LBM produces modern materials using the 3D printing method, and together with cooperating institutions we produce materials using SPS and HIP methods. The cooperation is carried out with leading Polish universities and institutes (PW, AGH, WAT, IPPT, ITME) and international scientific institutes (CEA, VTT, IIT, ORNL, JRC, JAEA or CHRTEM).
LBM actively cooperates with the Ministry of Science and Higher Education, which supports the development of new research methods and allows for the maintenance of modern scientific equipment, including the only group of hot chambers in Poland with a protection of 100 Ci, 3.7 TBq. The chambers are equipped with advanced measuring equipment and enable a number of measurements of the physical, mechanical and structural properties of active materials. LBM Was designed and built in the 1980 s to test the so-called witness samples from nuclear power reactors. The assessment of the properties of witness samples carried out over the years of the reactor’s operation enables the assessment of the degradation state of the reactor’s structural materials. Therefore, it is one of the procedures for monitoring the operational safety of a nuclear installation.