Filtry
Irradiation-assisted stress corrosion cracking of Ti-stabilized austenitic stainless steel
and pressurized water PWRs of the western type. In the eastern type of PWRs, also called WWERs, IASCC has been reported in only a few cases. The main differences between the PWRs) and the operational environment. New crack...
Materials engineering
- 2019 •
- D •
- Odkaz
Rok uplatnění
D - Stať ve sborníku
Výsledek na webu
WWER Type RVI
The objective of chapters of this publication is to update relevant sections of the existing IAEA-TECDOC-1119 in order to provide current ageing management guidance for PWR RVIs to all involved in the operation and regulation of PWRs
JF - Jaderná energetika
- 2007 •
- C
Rok uplatnění
C - Kapitola v odborné knize
High conversion Th-U233 fuel for current generation of PWRs: Part I - Assembly level analysis
This study explores the possibility of designing a high conversion (HC) Th-U233 core for current generation of Pressurized Water Reactors (PWRs). Increasing the conversion ratio in existing PWRs can potentially improve the utilizati...
JF - Jaderná energetika
- 2014 •
- Jx •
- Odkaz
Rok uplatnění
Jx - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)
Výsledek na webu
High conversion Th-U233 fuel for current generation of PWRs: Part II-3D full core analysis
This study explores a possibility of designing a high conversion (HC) Th-U233 core for current generation of pressurized water reactors (PWRs). Increasing the conversion ratio in existing PWRs can potentially improve the utilization...
JF - Jaderná energetika
- 2014 •
- Jx •
- Odkaz
Rok uplatnění
Jx - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)
Výsledek na webu
LEAKBOX 2009
Software for activity distribution prediction in PWR hermetical area.
JF - Jaderná energetika
- 2009 •
- R
Rok uplatnění
R - Software
Caracteristic of Fuel Cycle with Reactors PWR and GENIV
Report descibed characteristics of PWR and GEN IV reactors fuel cycle.
JF - Jaderná energetika
- 2007 •
- O
Rok uplatnění
O - Ostatní výsledky
Common comparison of the irradiation embrittlement of WWER/PWR reactor pressure vessel steels
The paper presents the immediate comparison of Tk shifts due to neutron irradiation for WWER and PWR RPV materials and common experimental data analysis. The PWR range.For both PWR and WWER RPV material types, there is a si...
JF - Jaderná energetika
- 2014 •
- Jx •
- Odkaz
Rok uplatnění
Jx - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)
Výsledek na webu
Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: PWR Pressure Vessels: (2007 Update)
The objective of this publication is to update IAEA-TECDOC-1120 in order to provide current ageing management guidance for PWR RPVs.
JF - Jaderná energetika
- 2007 •
- B
Rok uplatnění
B - Odborná kniha
Corrosion of Zr-Nb and Zr-Sn alloys under simulated environment of PWR reactor Corrosion of Zr-Nb and Zr-Sn alloys under simulated environment of PWR reactor Corrosion of Zr-Nb and Zr-Sn alloys under
in the environment simulating the cooling agent of PWR reactor. The goal of long-term experiments...
JK - Koroze a povrchové úpravy materiálu
- 2015 •
- Jx
Rok uplatnění
Jx - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)
PWR 630 - axial fan with curved stator blades
PWR 630 is an aluminium alloy high pressure axial fan with curved stator blades, with Multiwing impeller-diameter 630, power 30 kW, with asynchronous motor 3x400v, 50 hz....
JQ - Strojní zařízení a nástroje
- 2013 •
- Gfunk
Rok uplatnění
Gfunk - Funkční vzorek
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