Results 21 to 30 of about 391 (181)

Uranium Recovery from Phosphates for Self‐Sufficient Nuclear Power in the Eastern Mediterranean

open access: yesScience and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022
Production of phosphate fertilizers (PF), without uranium recovery, amounts to dispersing uranium compounds on agricultural fields. These compounds are naturally hidden in phosphate rock deposits prior to processing. Such a dispersion is a cumulative environmental damage, that may become rather catastrophic in few hundred years, under the current rates
Nassar H. S. Haidar, Guglielmo Lomonaco
wiley   +1 more source

CANDU Safety R&D Status, Challenges, and Prospects in Canada

open access: yesScience and Technology of Nuclear Installations, 2015
In Canada, safe operation of CANDU (CANada Deuterium Uranium; it is a registered trademark of Atomic Energy of Canada Limited) reactors is supported by a full-scope program of nuclear safety research and development (R&D) in key technical areas.
W. Shen, F. Doyle
doaj   +1 more source

CURRENT STATUS OF INTEGRITY ASSESSMENT BY SIPPING SYSTEM OF SPENT FUEL BUNDLES IRRADIATED IN CANDU REACTOR

open access: yesNuclear Engineering and Technology, 2014
In terms of safety and the efficient management of spent fuel storage, detecting failed fuel is one of the most important tasks in a CANada Deuterium Uranium (CANDU) reactor operation.
JONG-YOUL PARK   +2 more
doaj   +1 more source

CANDU FIRE DATABASE

open access: yesCNL Nuclear Review, 2019
The Nuclear Energy Agency (NEA) is a specialized agency within the Organization for Economic Co-operation and Development (OECD). The International Fire Data Exchange Project (OECD FIRE) was designed by the NEA to encourage multilateral co-operation in the collection and analysis of data relating to fire events in nuclear power plants.
Hossam Shalabi, George Hadjisophocleous
openaire   +1 more source

EVALUATION OF THE APPLICABLE REACTIVITY RANGE OF A REACTIVITY COMPUTER FOR A CANDU-6 REACTOR

open access: yesNuclear Engineering and Technology, 2014
Recently, a CANDU digital reactivity computer system (CDRCS) to measure the worth of the liquid zone controller in a CANDU-6 was developed and successfully applied to a physics test of refurbished Wolsong Unit 1.
EUN KI LEE, DONG HWAN PARK, WHAN SOO LEE
doaj   +1 more source

Effect of DUPIC Cycle on CANDU Reactor Safety Parameters

open access: yesNuclear Engineering and Technology, 2016
Although, the direct use of spent pressurized water reactor (PWR) fuel in CANda Deuterium Uranium (CANDU) reactors (DUPIC) cycle is still under investigation, DUPIC cycle is a promising method for uranium utilization improvement, for reduction of high ...
Nader M.A. Mohamed, Alya Badawi
doaj   +1 more source

ROMANIAN EXPERIENCE ON CANDU 600 FUELLING MACHINE TESTING [PDF]

open access: yesAnnals: Series on engineering sciences (Academy of Romanian Scientists), 2013
The CANDU 600 Fuelling Machine is a complex mechanism which must run in safety conditions and with high reliability in the CANDU Reactor. The testing and commissioning process of this nuclear equipment meets the high standards of NPP’s requirements using
Şerban Constantin VALECA   +2 more
doaj  

Sensitivity Analysis of Continuous-energy Nuclear Data and Its Application in AP1000

open access: yesYuanzineng kexue jishu, 2022
AP1000 is the typical third-generation nuclear power technology. The sensitivity analysis of continuous-energy nuclear data for AP1000 is the basis of uncertainty quantification which plays an important role in subsequent safety analysis for AP1000 ...
HUANG Jinlong;CAO Liangzhi;HE Qingming;LI Jie;SHEN Wei
doaj  

Uncertainties impact on the major FOMs for severe accidents in CANDU 6 nuclear power plant

open access: yesNuclear Engineering and Technology, 2023
In the nuclear safety studies, a new trend refers to the evaluation of uncertainties as a mandatory component of best-estimate safety analysis which is a modern and technically consistent approach being known as BEPU (Best Estimate Plus Uncertainty).The ...
R.M. Nistor-Vlad, D. Dupleac, G.L. Pavel
doaj   +1 more source

Analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the CANDU reactor [PDF]

open access: yesNuclear Technology and Radiation Protection, 2017
This study presents the determination of fuel rejuvenation times in a D-T fusion breeder reactor fuelled with a mixture of natUO2 and ThO2 for multi-reuse of nuclear fuels in CANDU-37 reactors.
Bakir Gizem, Yapici Huseyin
doaj   +1 more source

Home - About - Disclaimer - Privacy