Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned reactor-Reference-Cited by-同舟云学术

Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned reactor

Published:2011-09 Issue:1-2 Volume:416 Page:111-116
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Ulbricht A.,Altstadt E.,Bergner F.,Viehrig H.-W.,Keiderling U.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference23 articles.

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4. Y.N. Korolev, Y.I. Strombakh, Y.A. Nikolaev, Y.A. Krasikov, P.A. Platonov, in: M.A. Sokolov, J.D. Landes, G.E. Lucas (Eds.), Small specimens test techniques: Fourth volume, ASTM STP 1418, American Society for Testing and Materials, West Conshohocken, 2002.

5. Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

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1. Recovery of neutron-irradiated VVER-440 RPV base metal and weld exposed to isothermal annealing at 343°C up to 2,000 h;Frontiers in Nuclear Engineering;2024-08-16

2. Elemental distribution in a decommissioned high Ni and Mn reactor pressure vessel weld metal from a boiling water reactor;Nuclear Materials and Energy;2023-09

3. Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels;Nuclear Materials and Energy;2021-03

4. The dominant mechanisms for the formation of solute-rich clusters in low-Cu steels under irradiation;Materials Today Energy;2020-09

5. On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models;Journal of Nuclear Materials;2019-12