Results 101 to 110 of about 2,554,621 (223)

TEM Examination of M5 Zirconium Alloy Cladding of Spent Fuel Rod

Yuanzineng kexue jishu
The zirconium alloy cladding of PWR fuel rods which undergo high neutron irradiation during service, will cause significant changes in its microstructure, thereby affecting its macroscopic performance. Therefore, the study of neutron irradiation behavior
QIAN Jin, BIAN Wei, GUO Yifan, WANG Xin, LIANG Zhengqiang
doaj   +1 more source

2D longitudinal modeling of heat transfer and fluid flow during multilayered [PDF]

, 2012
version post-print de l'article : JLA Vol : 24 Iss:3. 2D longitudinal modeling of heat transfer and fluid flow during multilayered direct laser metal deposition processDerived from laser cladding, the Direct Laser Metal Deposition (DLMD) process is ...
CARRON, Denis, LE MASSON, Philippe, GHARBI, Myriam, PEYRE, Patrice, FABBRO, Rémy, CARIN, Muriel, MORVILLE, Simon   +6 more
core  

Raman amplification and pulsed lasing in cladding-pumped germanosilicate fiber

We report for the first time Raman amplification in a cladding-pumped fiber. The double-clad germanosilicate fiber was pumped by a Q-switched Er-Yb co-doped fiber laser at 1570 nm. The power conversion efficiency was up to 36%, with a slope of 64%
Selvas, R., Hanna, D.C., Nilsson, J., Grudinin, A.B., Sahu, J.K., Jang, J.N.   +5 more
core   +1 more source

Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT

, 2019
The OpenFOAM Fuel BEhavior Analysis Tool, or OFFBEAT, is a new fuel performance code under collaborative development at the Laboratory for Reactor Physics and Systems Behaviour of the École Polytechnique Fédérale de Lausanne and at the Paul Scherrer ...
Clifford, Ivor (author), Scolaro, Alessandro (author), Fiorina, Carlo (author), Pautz, Andreas (author)   +3 more
core   +1 more source

CORE SHAPE OF FUEL ELEMENTS CLAD WITH ZIRCONIUM ALLOY [PDF]

, 1953
Holladay, J.W., Kura, J.G., Jackson, J.H.   +2 more
openaire   +2 more sources

MECHANICAL CLADDING-FUEL INTERACTIONS DURING THERMAL CYCLING OF METAL-CLAD FUEL ELEMENTS [PDF]

, 1965
openaire   +2 more sources

Fuel performance beyond design - Exploring the limits

, 2010
Lead test assemblies from Westinghouse have been irradiated in the power reactor of Kernkraftwerk Leibstadt AG (KKL). Based on the poolside inspection result rods were extracted and transported to the hot cell of the Paul Scherrer Institut.
Gavillet, Didier (author), Hallstadius, Lars (author), Sugiyama, Tomoyuki (author), Wiesenack, Wolfgang (author), Abolhassani, Sousan (author), Limbäck, Magnus (author), Tverberg, Terje (author), Nagase, Fumihisa (author), Valizadeh, Sima (author), Wright, Jonathan (author), Ledergerber, Guido (author)   +10 more
core   +1 more source

A CLADDING THICKNESS TESTER FOR FLAT FUEL ELEMENTS [PDF]

, 1955
openaire   +2 more sources

3D hydrides arrangement in fuel cladding tubes and temporal development of hydrogen relocation in liner cladding investigated with neutron imaging

The present work concerns the detection and visualization of hydrogen and hydrides in unirradiated nuclear fuel claddings, focusing on the temporal development of hydrogen relocation and precipitation, plus the rearrangement of hydrides in three ...
Yetik, O. (author), Meyer, M. (author), Mota, D. (author), Trtik, P. (author), Bertsch, J. (author), Zubler, R. (author), Duarte, L. (author)   +6 more
core   +1 more source

A Modified Temperature-Dependent Elastoplastic Constitutive Model for Blister Growth in Irradiated Al6061 Cladding. [PDF]

Materials (Basel)
Luo Q, Wang W, Chen Y, Tang F.
europepmc   +1 more source