Results 11 to 20 of about 8,761,998 (286)

Local Burn-Up Effects in the NBSR Fuel Element [PDF]

, 2013
This study addresses the over-prediction of local power when the burn-up distribution in each half-element of the NBSR is assumed to be uniform. A single-element model was utilized to quantify the impact of axial and plate-wise burn-up on the power distribution within the NBSR fuel elements for both high-enriched uranium (HEU) and low-enriched uranium (
Brown, N. R., Hanson, A. L., Diamond, D. J.   +2 more
openaire   +4 more sources

Microhardness and Young's modulus of high burn-up UO2 fuel [PDF]

Journal of Nuclear Materials, 2016
AbstractVickers microhardness (HV0.1) and Young's modulus (E) measurements of LWR UO2 fuel at burn-up ≥60 GWd/tHM are presented. Their ratio HV0.1/E was found constant in the range 60–110 GWd/tHM. From the ratio and the microhardness values vs porosity, the Young's modulus dependence on porosity was derived and extended to the full radial profile ...
Cappia, F., PIZZOCRI, DAVIDE, Marchetti, M., Schubert, A., Van Uffelen, P., LUZZI, LELIO, Papaioannou, D., Maciàn Juan, R., Rondinella, V. V.   +8 more
core   +3 more sources

Civil aircraft trajectory analyses - impact of engine degradation on fuel burn and emissions [PDF]

, 2013
Commercial aviation and air traffic is still expected to grow by 4-5% annually in the future and thus the effect of aircraft operation on the environment and its consequences for the climate change is a major concern for all parties involved in the ...
Venediger, Benjamin
core   +7 more sources

Triga Fuel Burn-Up Calculations Supported By Gamma Scanning

, 2009
High resolution gamma-ray spectroscopy based non-destructive methods is employed to measure spent fuel parameters. By this method, the axial distribution of Cesium-137 has been measured which results in an axial burn up profiles.
Khan, R., Böck, Helmuth, Karimzadeh, S., Villa, Mario   +3 more
core   +4 more sources

Long-term persistance of the pathophysiologic response to severe burn injury. [PDF]

, 2011
Main contributors to adverse outcomes in severely burned pediatric patients are profound and complex metabolic changes in response to the initial injury. It is currently unknown how long these conditions persist beyond the acute phase post-injury.
Kraft, Robert, Marc G Jeschke, David N Herndon, Felicia N Williams, Gabriela A Kulp, Ronald P. Mlcak, Oscar E. Suman, Felicia N. Williams, Jeschke Marc G., Kulp, Gabriela A., Celeste C. Finnerty, Suman, Oscar E., Gerd G. Gauglitz, Kulp Gabriela A., Marc G. Jeschke, Finnerty Celeste C., Gabriela A. Kulp, Gerd G Gauglitz, Mlcak, Ronald P., David N. Herndon, Gauglitz, Gerd G., Herndon, David N., Jeschke, Marc G., Herndon David N., Finnerty, Celeste C., Mlcak Ronald P., Ronald P Mlcak, Suman Oscar E., Williams, Felicia N., Kraft Robert, Williams Felicia N., Gauglitz Gerd G., Oscar E Suman, Celeste C Finnerty, Robert Kraft   +34 more
core   +2 more sources

Analisis Burn Up pada Reaktor Cepat Berpendingin Gas Menggunakan Bahan Bakar Uranium Alam

JIF (Jurnal Ilmu Fisika), 2015
Burn up analysis of gas cooled fast reactor (GCFR) with natural uranium fuel has been done. Burn up modification used in order to make reactor can be operated with natural uranium without enrichment.
Feriska Handayani Irka, Zaki Su’ud   +1 more
doaj   +1 more source

The high burn-up structure in nuclear fuel

Materials Today, 2010
During its operating life in the core of a nuclear reactor nuclear fuel is subjected to significant restructuring processes determined by neutron irradiation directly through nuclear reactions and indirectly through the thermo-mechanical conditions established as a consequence of such reactions.
Rondinella, Vincenzo V., Wiss, Thierry
openaire   +1 more source

Automated system for determining the burnup of spent nuclear fuel

Tekhnologiya i Konstruirovanie v Elektronnoi Apparature, 2014
The authors analyse their experience in application of semiconductor detectors and development of a breadboard model of the monitoring system for spent nuclear fuel (SNF). Such system should use CdZnTe-detectors in which one-charging gathering conditions
V. A. Mokritskii, O. V. Maslov, O. V. Banzak   +2 more
doaj   +1 more source

Shielding Design and Dose Evaluation for HTR-PM Fuel Transport Pipelines by QAD-CGA Program

Science and Technology of Nuclear Installations, 2021
The spherical fuel elements are adopted in the high-temperature gas-cooled reactor pebble-module (HTR-PM). The fuel elements will be discharged continuously from the reactor core and transported into the fuel transport pipelines during the reactor ...
Sheng Fang, Jianzhu Cao, Wenqian Li, Chen Luo, Feng Yao, Xiaofan Li, Kai Li   +6 more
doaj   +1 more source

Modeling of Pore Coarsening in the Rim Region of High Burn-up UO2 Fuel

Nuclear Engineering and Technology, 2016
An understanding of the coarsening process of the large fission gas pores in the high burn-up structure (HBS) of irradiated UO2 fuel is very necessary for analyzing the safety and reliability of fuel rods in a reactor.
Hongxing Xiao, Chongsheng Long
doaj   +1 more source