Zobrazeno 1 - 10 of 29 pro vyhledávání: '"Harm, U."'
1
Electrochemical zinc corrosion studies in boric acid containing electrolytes (datafiles)
Autor: Harm, U., Kryk, H., Hampel, U.
Publikováno v: Publication date: 2022-03-18 Open accessDOI: 10.14278/rodare.1485Versions: 10.14278/rodare.1486License: CC-BY-4.0
Datafiles for planned publication with the title: "Electrochemical zinc corrosion studies in boric acid containing electrolytes" Further descriptions of the methods and parameters for the conducted electrochemical experiments as well as the allocatio
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______4577::c4102edefc6d53fef62831dafb08c580
https://www.hzdr.de/publications/Publ-34398-1
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2
LOCA scenario-related zinc borate precipitation studies at lab scale
Autor: Harm, U., Kryk, H., Wiezorek, M., Hampel, U.
Publikováno v: 50th Annual Meeting on Nuclear Technology (AMNT 2019), 07.-08.05.2019, Berlin, DeutschlandProceedings of the 50th Annual Meeting on Nuclear Technology (AMNT 2019), Berlin: INFORUM Verlags-und Verwaltungsgesellschaft mbH, 978-3-926956-95-8
50th Annual Meeting on Nuclear Technology (AMNT 2019), 07.-08.05.2019, Berlin, Deutschland
During the sump recirculation operation after a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), coolant spilling out of the leak in the primary cooling circuit is collected in the reactor sump and recirculated to the
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::f05e03ab4f0d2940d1261960d37b5802
https://www.hzdr.de/publications/Publ-29478-2
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3
Lokale Effekte im DWR-Kern infolge von Zinkborat-Ablagerungen nach KMV (Projekt-Abschlussbericht BMWi-Vorhaben 'Zinkborat')
Autor: Hampel, U., Harm, U., Kryk, H., Ding, W., Wiezorek, M., Unger, S.
Publikováno v: Hannover: TIB Hannover, 2019178 Seiten
Im Falle eines Kühlmittelverluststörfalles (KMV) im Primärkühlkreislauf von DWR hat durch Korrosion im Kühlmittel (KM) freigesetztes Zink das Potenzial, in den Reaktorkern zu gelangen und sich bei Erwärmung (z.B. in Heißkanälen) in feste Korr
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______4577::db671274a5d4cca1f7e83712292b1dab
https://www.hzdr.de/publications/Publ-29479-1
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4
Electrochemical studies on zinc in boric acid containing electrolytes
Autor: Harm, U., Kryk, H., Hampel, U.
Publikováno v: Electrochemistry 2018, 24.-26.09.2018, Ulm (Universität Ulm), Deutschland
During the sump recirculation phase after a leak in the primary cooling circuit of a pressurized water reactor (PWR), corrosion of hot-dip galvanized containment internals (e.g. grating treads, supporting grids of sump strainers) in the boric acid co
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______4577::97458175119864e9d5b65e5049f2657e
https://www.hzdr.de/publications/Publ-28112-1
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5
Generic zinc corrosion studies at PWR LOCA conditions
Autor: Harm, U., Kryk, H., Wiezorek, M., Hampel, U.
Publikováno v: 48. Jahrestagung Kerntechnik (Annual Meeting on Nuclear Technology / AMNT 2017), 16.-17.05.2017, Berlin, DeutschlandGeneric Zinc Corrosion Studies At PWR LOCA Conditions, Berlin: INFORUM Verlags-und Verwaltungsgenossenschaft mbH, 978-3-926956-96-5
48. Jahrestagung Kerntechnik (Annual Meeting on Nuclear Technology / AMNT 2017), 16.-17.05.2017, Berlin, Deutschland
During the sump recirculation phase after loss-of-coolant accidents (LOCA) in pressurized water reactors (PWR), coolant spilling out of the leak in the primary cooling circuit is collected in the reactor sump and recirculated to the reactor core by r
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::eea6ea49e6b7c0cd44fb96a934518321
https://www.hzdr.de/publications/Publ-24444-1
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6
Interactions of coolants with hot-dip galvanized materials after loss-of-coolant accidents in pressurized water reactors
Autor: Harm, U., Kryk, H., Hampel, U.
Publikováno v: The Energy and Materials Research Conference (EMR 2017), 05.-07.04.2017, Lissabon (Lisbon), PortugalBook of Abstracts
The Energy and Materials Research Conference (EMR 2017), 05.-07.04.2017, Lisabon (Lisbon), Portugal
During the sump recirculation phase after loss-of-coolant accidents (LOCA) in pressurized water reactors, coolant spilling out of the leak in the primary cooling circuit is collected in the reactor sump and recirculated to the reactor core by residua
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https://www.hzdr.de/publications/Publ-25708-1
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7
Akademický článek
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8
Reducing in-core zinc borate precipitation after LOCA in pressurized water reactors
Autor: Kryk, H., Harm, U., Hampel, U.
Publikováno v: 47th Annual Meeting on Nuclear Technology, 10.-12.05.2016, Hamburg, GermanyProceedings 47th Annual Meeting on Nuclear Technology, Berlin: INFORUM Verlags-und Verwaltungsgesellschaft mbH, 978-3-926956-97-2
47th Annual Meeting on Nuclear Technology, 10.-12.05.2016, Hamburg, Germany
During the sump recirculation phase after loss-of-coolant accidents (LOCAs) in pressurized water reactors (PWRs), coolant spilling from the leak in the primary cooling circuit is collected in the reactor sump and recirculated to the reactor core by r
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::416753d461dd135032f4adea0cd9f704
https://www.hzdr.de/publications/Publ-23690-2
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9
Analysis of SAM Coatings for Dropwise Condensation in Passive Safety Systems
Autor: Unger, S., Sarker, D., Harm, U., Hampel, U.
Publikováno v: 47th Annual Meeting on Nuclear Technology, 10.-12.05.2016, Hamburg, DeutschlandProceedings of the 47th Annual Meeting on Nuclear Technology
47th Annual Meeting on Nuclear Technology, 10.-12.05.2016, Hamburg, Deutschland
Passive safety systems of spent fuel pools are one key technology for further improvement of the reliability of nuclear power plants. These systems transfer high amount of heat, while using air as a heat sink. For that reason the overall temperature
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::d688ef450c376f7d3c0982e10a63c5b3
https://www.hzdr.de/publications/Publ-24312-2
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10
Partikelentstehung und -transport im Reaktorwasser von DWR nach Kühlmittelverluststörfällen (KMV) - Untersuchungen im Labormaßstab
Autor: Harm, U., Kryk, H., Hampel, U., Seliger, A., Renger, S., Kästner, W.
Publikováno v: Wasser im Kraftwerk und in der Energietechnik, Zittauer Kraftwerkschemisches Kolloquium, 23.09.2016, Zittau, Deutschland
Wasser im Kraftwerk und in der Energietechnik, Zittauer Kraftwerkschemisches Kolloquium, 22.-23.09.2016, Zittau, DeutschlandProceedings des Zittauer Kraftwerkschemischen Kolloquiums
Im Rahmen der nuklearen Sicherheitsforschung des Bundesministeriums für Wirtschaft und Energie (BMWi) erfolgten an der Hochschule Zittau/Görlitz (HSZG) in Kooperation mit der Technischen Universität Dresden (TUD) und dem Helmholtz-Zentrum Dresden-
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::4c29358c44db7a76185e6e7e8dec6949
https://www.hzdr.de/publications/Publ-24838-2
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