Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Joerg Konheiser"'
Publikováno v:
Journal of Nuclear Science and Technology 54(2017)2, 188-195
This work shows the impact of potential displacements of the fuel assembly positions in the reactor core on the signal values of the ex-core instrumentation of a KWU – type pressurized water reactor in order to understand in detail the impact on th
Publikováno v:
Journal of Nuclear Science and Technology. 53:1715-1722
The aeroball measurement system (AMS) is an important in-core instrumentation in German pressurized water reactors. Therefore, it is essential to know the possible uncertainties of this system. One is the lack of knowledge of the positions of balls i
Publikováno v:
EPJ Web of Conferences, Vol 106, p 02006 (2016)
Fifteenth International Symposium on Reactor Dosimetry, 18.-23.05.2014, Aix-en-Provence, FranceEPJ Web of Conferences, Les Ulis Cedex: EDP Sciences, 978-2-7598-1929-4
Fifteenth International Symposium on Reactor Dosimetry, 18.-23.05.2014, Aix-en-Provence, France
Fifteenth International Symposium on Reactor Dosimetry, 18.-23.05.2014, Aix-en-Provence, FranceEPJ Web of Conferences, Les Ulis Cedex: EDP Sciences, 978-2-7598-1929-4
Fifteenth International Symposium on Reactor Dosimetry, 18.-23.05.2014, Aix-en-Provence, France
The reactor pressure vessel (RPV) represents one of the most important safety components in a nuclear power plant. Therefore, surveillance specimen (SS) programs for the RPV material exist to deliver a reliable assessment of RPV residual lifetime. Th
Publikováno v:
13th International Symposium on Reactor Dosimetry, 25.-31.05.2008, Alkmaar, NetherlandsReactor Dosimetry State of the Art 2008, New Jersey London Singapore: World Scientific Publishing Co. Pte. Ltd., 13 978-981-4271-10-3, 688-699
13th International Symposium on reactor Dosimetry, 25.-31.05.2008, Alkmaar, Netherlands
13th International Symposium on reactor Dosimetry, 25.-31.05.2008, Alkmaar, Netherlands
The support structure of a reactor pressure vessel experiences a high mechanical stress during reactor operations. In addition, supposed accident conditions and ferritic steel properties result in a low limiting value for the ductile-to-brittle trans
Publikováno v:
Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues.
Between 1973 and 1990 4 units of the Russian NPP type WWER-440/230 were operated in Greifswald (former GDR). The operation was stopped after the German reunification, because the units did not completely follow western nuclear safety standards. Mater
Autor:
Bertram Boehmer, W. Hansen, Klaus Noack, Ingrid Stephan, S. Unholzer, Anatoli Rogov, Joerg Konheiser, Martin Grantz, Hans-Christoph Mehner, Dietmar Hinke
Publikováno v:
AIP Conference Proceedings.
Neutron and gamma spectra were measured behind and inside of modules consisting of variable iron and water slabs that were installed in radial beams of the zero‐power training and research reactors AKR of the Technical University Dresden and ZLFR o
Autor:
Bertram Boehmer, Joerg Konheiser, Klaus Noack, Anatoli Rogov, Ingrid Stephan, Wolfgang Hansen, Dietmar Hinke, Siegfried Unholzer, Martin Grantz, Hans-Christoph Mehner
Publikováno v:
12th International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, United States
Journal of ASTM International 3(2006)8
12 th International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, United StatesReactor Dosimetry: 12th International Symposium, West Conshohocken: ASTM, 978-0-8031-3412-6
Journal of ASTM International 3(2006)8
12 th International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, United StatesReactor Dosimetry: 12th International Symposium, West Conshohocken: ASTM, 978-0-8031-3412-6
Gamma and neutron flux spectra were measured inside and behind various combined iron, steel and water slabs, which were set up in the radial beams of the zero-power training and research reactors AKR of the Technical University Dresden and ZLFR of th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::36f3f3bd437271066dc000106a974761
https://www.hzdr.de/publications/Publ-7473-1
https://www.hzdr.de/publications/Publ-7473-1
Publikováno v:
International Conference on Nuclear Data for Science and Technology, 7-12th Oct. 2001, Tsukuba, Japan, Proceedings in the Journal of Nuclear Science and Technology, Supplement 2, p. 1006-1009 (August 2002)
The fast neutron induced embrittlement of the reactor pressure vessel (RPV) is the main cause limiting the lifetime of many types of nuclear reactors, especially of the VVER type, produc-ing most of the nuclear energy in Russia and seven other countr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3ea56c062afb5912f38e9b94ff88ccb0
https://www.hzdr.de/publications/Publ-4119-1
https://www.hzdr.de/publications/Publ-4119-1