Results 71 to 80 of about 821 (181)
FISSION PRODUCT RELEASE FROM HIGH AND LOW-ENRICHED URANIUM FUELS OF THE IVG.1M RESEARCH REACTOR
The research involved conducting resource tests on two experimental water-cooled technological channels (WCTCs) utilizing low-enriched uranium (LEU) fuel within the IVG1.M research reactor.
B.S. Medetbekov +3 more
doaj +1 more source
FISSION PRODUCT DIFFUSION THROUGH CLAD CERMET FUEL ELEMENTS
Small plates of UO/sub 2/ clad with 5 mils of 304L stainless steel were irradiated, cooled, and placed in an experimental apparatus at high temperature swept out by N/sub 2/ gas. No increase in activity was observed, indicating that no diffusion through the clad took place. These results disagree with those of previous experiments, however, and must be
L P Crocker, C E Creek
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Experimental Study on PCMI Behavior of RIA outside Reactor
The performance of zirconium alloy cladding has always been a concern during reactor accidents. Ensuring the safe operation of high fuel consumption under reactivity initiated accident condition is also the core issue that scholars from various countries
HAO Sijia, DING Xijia, HU Zhen, XU Qian, HAN Zhijie
doaj +1 more source
TEM Examination of M5 Zirconium Alloy Cladding of Spent Fuel Rod
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
Numerical simulation method of the failure behavior of the UMo-Al monolithic fuel element
The UMo-Al monolithic fuel element has a special failure mode of blistering on the cladding surface under high temperature and high burn-up conditions.
Zhifeng Zheng +6 more
doaj +1 more source
PROCESS FOR THE DISSOLUTION OF ALUMINUM-CLAD THORIA FUEL ELEMENTS. [PDF]
Phillips, J. F., Huber, H. D.
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MECHANICAL CLADDING-FUEL INTERACTIONS DURING THERMAL CYCLING OF METAL-CLAD FUEL ELEMENTS [PDF]
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CORE SHAPE OF FUEL ELEMENTS CLAD WITH ZIRCONIUM ALLOY [PDF]
Holladay, J.W. +2 more
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Review of Recent Advances in Cold-Sprayed Coatings for Accident-Tolerant Fuel Cladding. [PDF]
Mou Y +10 more
europepmc +1 more source

