Results 21 to 30 of about 1,590,279 (298)

Testing of the ABBN-RF multigroup data library in photon transport calculations

open access: yesEPJ Web of Conferences, 2017
Gamma radiation is produced via both of nuclear fuel and shield materials. Photon interaction is known with appropriate accuracy, but secondary gamma ray production known much less. The purpose of this work is studying secondary gamma ray production data
Koscheev Vladimir   +3 more
doaj   +1 more source

An introduction to nuclear power : science, technology and UK policy context [PDF]

open access: yes, 2012
This paper is the first in a series of 8 that make up the evidence base for SDC report 'The role of nuclear power in a low carbon economy'.Publisher ...
Sustainable Development Commission
core   +2 more sources

Licensed reactor nuclear safety criteria applicable to DOE reactors [PDF]

open access: yes, 1991
The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned ...

core   +1 more source

Test tasks for verification of program codes for calculation of neutron-physical characteristics of the BN series reactors

open access: yesEPJ Web of Conferences, 2017
System of test tasks is presented with the fast reactor BN-1200 with nitride fuel as prototype. The system of test tasks includes three test based on different geometric models.
Tikhomirov Georgy   +5 more
doaj   +1 more source

Examination of total cross section resonance structure of niobium and silicon in neutron transmission experiments

open access: yesEPJ Web of Conferences, 2017
The neutron transmission experiments are one of the main sources of information about the neutron cross section resonance structure and effect in the self-shielding. Such kind of data for niobium and silicon nuclides in energy range 7 keV to 3 MeV can be
Andrianova Olga   +2 more
doaj   +1 more source

Heat transfer characteristics for multi-silicon ingots irradiation in a typical research reactor

open access: yesInternational Journal of Thermofluids, 2023
A computational fluid dynamics (CFD) study is conducted for silicon ingot irradiation facility in a typical material testing reactor (MTR). The ingots are placed inside the irradiation device in staggered and in-line bundles.
Said M.A. Ibrahim   +2 more
doaj   +1 more source

Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage

open access: yesEPJ Web of Conferences, 2017
Decay heat power of actinides and fission products from spent nuclear fuel of power VVER-1000 type reactors at long-term storage is calculated. Two modes of storage are considered: mode in which single portion of actinides or fission products is loaded ...
Ternovykh Mikhail   +3 more
doaj   +1 more source

Evaluation of isotopic composition of fast reactor core in closed nuclear fuel cycle

open access: yesEPJ Web of Conferences, 2017
The strategy of the development of nuclear power in Russia provides for use of fast power reactors in closed nuclear fuel cycle. The PRORYV (i.e. «Breakthrough» in Russian) project is currently under development.
Tikhomirov Georgy   +4 more
doaj   +1 more source

Characteristics of iron and nickel diffusion in molten lead-bismuth eutectic

open access: yesMechanical Engineering Journal, 2015
The characteristics of iron (Fe) and nickel (Ni) diffusion in molten lead-bismuth eutectic (LBE) were investigated experimentally by using capillary method.
Yun GAO, Minoru TAKAHASHI, Masao NOMURA
doaj   +1 more source

Consistent neutron-physical and thermal-physical calculations of fuel rods of VVER type reactors

open access: yesEPJ Web of Conferences, 2017
For modeling the isotopic composition of fuel, and maximum temperatures at different moments of time, one can use different algorithms and codes. In connection with the development of new types of fuel assemblies and progress in computer technology, the ...
Tikhomirov Georgy   +3 more
doaj   +1 more source

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