Investigation on the influence of flux density on RPV steel embrittlement
Creators
- 1. GKSS-Forschungszentrum Geesthacht G.m.b.H., Geesthacht-Tesperhude (Germany, F.R.). Inst. fuer Werkstofftechnologie und Chemie
Description
Recent US results from surveillance programs indicate an influence of flux density on transition temperature shift induced by fast neutron irradiation. Own irradiation experiments on ASTM A533 gr B cl 1 steel from HSST plate 03 have been reevaluated but no flux density could be found. Taking into account the maximum experimental error upper limits have been estimated for the constants describing annealing according to simple models; corresponding ΔTT versus fluence curves for different flux densities have been calculated. To prove the assumptions and to better quantify the estimated constants an irradation experiment is being prepared in which the neutron flux density and the target fluence will be varied. The materials to be investigated are heats of 20MnMoNi55 and 22NiMoCr37 and corresponding weld material. (orig./HP)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- GKSS--79/E/55
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 13658782
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- DAMAGING NEUTRON FLUENCE; EMBRITTLEMENT; FAST NEUTRONS; FLUX DENSITY; IRRADIATION; NEUTRON BEAMS; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; REACTOR COMPONENTS; STEEL-ASTM-A533
- Descriptors DEC
- ALLOYS; BARYONS; BEAMS; CARBON ADDITIONS; CONTAINERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; NEUTRON FLUENCE; NEUTRONS; NUCLEON BEAMS; NUCLEONS; PARTICLE BEAMS; RADIATION EFFECTS; RADIATION FLUX; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- Reprint from: Commission of the European Communities (ed.): 'Dosimetry methods for fuels, cladding and structural materials'. Proceedings of the 3. ASTM-Euratom symposium on reactor dosimetry, Ispra, Italy, 1-5 October 1979. EUR 6813, v. 1, 1980.