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#0157Spallation of Tungsten

Spallation Experiment with Tungsten Target.

#0183Fission Spectra of Minor Actinides

Measurements of the Fission Neutron Spectra of the Minor Actinides. Spontaneous Fission of Curium Isotopes.

#0183-2Fission Spectra of Minor Actinides

Measurements of the Fission Neutron Spectra of the Minor Actinides. Spontaneous Fission of Pu-240. 242 and Thermal Neutron Induced Fission of Cm-243, 245.

#0304Accelerator-Based Measurements of Minor Actinides Cross-Sections

Measurements and Analysis of Basic Nuclear Data for Minor Actinides

#0371Pu-Utilization in LWR Experiments

Critical Experiments for the Pu- Utilization in LWR Type Reactors Using IPPE Facilities.

#0371-2Pu-Utilization in LWR Experiments

Critical Experiments for the Pu Utilization in VVER Type Reactors Using IPPE Facilities. (Phase 2-Basing of Three VVER FAs loading. Pre-SUPR Experimental Program)

#0471Neutron Fission and Capture Data

Measurements of Actinide Nuclear Data

#0477Proton Irradiated Targets

Spallation Experiments with Cylindrical Targets Irradiated by Medium-Energy Protons.

#0554Spontaneous Fission

Measurements of the Fission Neutron Multiplicity Distribution in Spontaneous Fission of Cm-244, Cm-248 and in Fission of U-233 and Pu-239 Induced by Thermal and Low Energy Neutrons.

#0554-2Spontaneous Fission

Measurements of the Fission Neutron Multiplicity Distribution in Spontaneous Fission of Cm-244, Cm-248 and in Fission of U-233 and Pu-239 Induced by Thermal and Low Energy Neutrons.

#0609Heavy Nuclei Neutron Cross-sections

Neutron Induced Fission Cross-sections of Some Actinides and other Heavy Nuclei in Energy Region 1-200 MeV.

#0910Nuclear Data of Vanadium

Execution of the Complex of Benchmark Experiments for Testing the Nuclear Data of Vanadium - Main Component of Low-Activation Structural Materials for Perspective Nuclear Energetics

#0910.2Nuclear Data for Vanadium

Execution of the Complex of Benchmark-Experiments for Testing the Nuclear Data of Vanadium - Main Component of Low-Activation Structural Materials for Advanced Nuclear Energy

#0964Fission Cross Sections Library

Development of Model Code and Theoretical Data Library on Heavy Nucleai Fission Cross-Sections in a Wide Energy Range

#1828Prompt Neutron Spectra of Minor Actinides

Measurements of the Prompt Neutron Spectra of Minor Actinides. Fast Neutron Induced Fission of 241Am and 243Am, Thermal Neutron Induced Fission of 243Cm

#1932Nuclear Safety for Advanced Neutron Sources

Theoretical and Experimental Substantiation of Nuclear Safety for Advanced Pulsed Neutron Sources

#1971Fission Cross Sections for Intermediate Neutron Energies

Neutron Induced Fission Cross-Sections of Pu-240, Am-243 and W in the Energy Range 1–200 MeV

#2213Fission Cross Sections of Tungsten Isotopes

Measurements of Proton- and Neutron-Induced Fission Cross Sections of Separated Tungsten Isotopes and Natural Tungsten in 50-200 MeV Energy Region

#2253Investigation of the Delayed Neutron Characteristics

Investigation of the Delayed Neutron Characteristics from the Fission of Compound Nuclei Th-233, U-234, U-235, Am-244, Np-238, Cm-246, Pa-233, Pa-234, Np-239, Np-240 at the Excitation Energies from 5 to 20 МeV

#2253.2Investigation of the Delayed Neutron Characteristics

Investigation of the Delayed Neutron Characteristics from the Fission of Compound Nuclei Th-233, U-234, U-235, Am-244, Np-238, Cm-246, Pa-233, Pa-234, Np-239, Np-240 at the Excitation Energies from 5 to 20 MeV

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The International Science and Technology Center (ISTC) is an intergovernmental organization connecting scientists from Kazakhstan, Armenia, Tajikistan, Kyrgyzstan, and Georgia with their peers and research organizations in the EU, Japan, Republic of Korea, Norway and the United States.

 

ISTC facilitates international science projects and assists the global scientific and business community to source and engage with CIS and Georgian institutes that develop or possess an excellence of scientific know-how.

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