Results 41 to 50 of about 12,769 (166)

Progress and Development Thinking of Dry Reprocessing Technology for Spent Nuclear Fuel from Fast Reactor

Yuanzineng kexue jishu
Dry reprocessing for spent nuclear fuel refers to a chemical process that involves treating spent nuclear fuel in non-aqueous media, recovering actinide elements such as uranium and plutonium, and properly disposing radioactive waste. It is a key step in
LIN Rushan, ZHONG Zhenya
doaj   +1 more source

On plutonium-241 and americium in the two-component nuclear energy system [PDF]

Nuclear Energy and Technology
The paper deals with the influence of the strategy for using separated plutonium from spent fuel of thermal and fast reactors, as well as homogeneous burning of americium in the BN reactor core on the balance of americium in the Russian nuclear fuel ...
Vladimir M. Troyanov, Andrey V. Gulevich, Olga S. Gurskaya, Viktor M. Dekusar, Vladimir A. Eliseev, Andrey L. Moseev   +5 more
doaj   +3 more sources

Comparative Analysis on the Characteristics of Liquid Lead and Lead–Bismuth Eutectic as Coolants for Fast Reactors

Energies
With the increasing global demand for sustainable energy, the importance of advanced nuclear technologies, such as fourth-generation reactors, has become increasingly prominent.
Mian Xing, Jihong Fan, Feng Shen, Daogang Lu, Linsen Li, Hui Yu, Jin Fan   +6 more
doaj   +1 more source

Analysis of radwaste accumulation in various scenarios of NP development [PDF]

Nuclear Energy and Technology
Within the framework of “Proryv” project a radiation-equivalent approach to radioactive waste management is being envisioned with U and Pu recycling and MA transmutation.
Andrey A. Kashirsky, Vladimir M. Solomatin, Sergey A. Panov, Elena A. Rodina, Alexander V. Egorov, Sergey A. Dmitriev, Alexey Y. Shulga   +6 more
doaj   +3 more sources

SUSTAINABLE NUCLEAR DEVELOPMENT IN ROMANIA [PDF]

Annals: Series on engineering sciences (Academy of Romanian Scientists), 2016
The paper presents the development of the nuclear power sector in Romania from the perspective of sustainable development. The current state is analysed and the expected future development is investigated. The implementation of ALFRED LFR demonstrator in
Serban Constantin VALECA, Ilie TURCU, Marin CONSTANTIN   +2 more
doaj  

Converting Maturing Nuclear Sites to Integrated Power Production Islands

Science and Technology of Nuclear Installations, 2011
Nuclear islands, which are integrated power production sites, could effectively sequester and safeguard the US stockpile of plutonium. A nuclear island, an evolution of the integral fast reactor, utilizes all the Transuranics (Pu plus minor actinides ...
Charles W. Solbrig
doaj   +1 more source

On the Fast Breeder Reactor

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1960
This report intended to review the physical characteristics and present status on the fast breeder reactor. In the first section, the neutron energy distribution, neutron spatial distribution, power distribution and some consideration of the design of the fast reactor are described in order to evaluate the breeding potentiality.
Shoji NOMOTO, Yorio H. TOMIOKA, Tomoo NAKAMURA   +2 more
openaire   +2 more sources

Verification and Validation of LoongSARAX Code for Nuclear Physics Analysis of Liquid Metal Cooled Fast Reactor

Yuanzineng kexue jishu
In fourth-generation reactors, fast reactors characterized by high average neutron flux, proliferating fission nuclear fuel, and transmutation of long-decay actinides have become the primary research focus in China.
LU Yao, DU Xianan, LI Aixin, GAO Jiehao, CHEN Wenjie, ZHENG Youqi, WANG Yongping, WU Hongchun
doaj   +1 more source

Uncertainty Analysis of Decay Heat Power after Fast Neutron Fission Based on Sensitivity/Uncertainty Method

Yuanzineng kexue jishu
To deal with the problem that notable light water reactor decay heat calculation standard is not suitable for fast reactor, this paper adopted the sensitivity/uncertainty (S/U) method to analyze the uncertainty introduced by nuclear data in the ...
WANG Fenglong1, YANG yong1, , HUANG Xiaolong2
doaj   +1 more source

MBSE-based passive residual heat removal system for lead-cooled fast reactors design requirement analysis

He jishu
BackgroundTraditional text-based system engineering in the design and application of passive residual heat removal systems (PRHRS) for lead-cooled fast reactors has several requirement problems, such as low development efficiency, a long iteration cycle,
TANG Mao, ZHAO Pengcheng, LI Wenjie, WANG Kai   +3 more
doaj   +1 more source