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Nuclear Data for Minor Actinides Transmutation


Measurement of Transmutation Properties of Minor Actinides Irradiated in Intermediate Reactor Neutron Spectrum

Tech Area / Field

  • FIR-EXP/Experiments/Fission Reactors
  • FIR-NOT/Nuclear and Other Technical Data/Fission Reactors

3 Approved without Funding

Registration date

Leading Institute
NIIAR (Atomic Reactors), Russia, Ulianovsk reg., Dimitrovgrad

Supporting institutes

  • Research Coordination Center on the Problem of Muon Catalyzed Fusion and Exotic Quantum Systems, Russia, Moscow


  • EURATOM-Ciemat, Spain, Madrid\nTokyo Institute of Technology / Research Laboratory for Nuclear Reactors, Japan, Tokyo\nJAERI / Tokai Research Establishment / Center for Proton Accelerator Facilities, Japan, Tokai Mura

Project summary

The main goal of the proposed project is to gain a set of the refined nuclear-physical actinide constants (neutron cross-sections predominantly) for an evaluated data file required for verification codes applied for validation of the ADS-burner concept. Moreover, the intention of the project is summarize the available data and to obtain new basic data on properties of molten salt fluoride compositions as the most promising candidates for the ADS-burner.

The following actinide isotope samples are supposed to be irradiated under the project:

- Uranium (238U);
- Neptunium (237Np);
- Plutonium (240Pu, 242Pu, 244Pu);
- Americium (241Am, 242mAm, 243Am);
- Curium (242Cm, 244Cm, 246Cm).

One of the targets will contain actinide fluoride distributed in fluoride salt solvent. This target will be used in the experiments on investigation of the actinide and basic FP distribution between liquid salt and liquid metal phases.

The irradiated targets will be studied to obtain the experimental data for calculating the effective neutron cross-sections of such actinides as 237Np, 241Am, 242mAm, 243Am, 242Cm, 243Cm, 244Cm, 245Cm, 246Cm, 247Cm, 248Cm, 249Bk, 250Cf, 251Cf, 252Cf making the maximum contribution to the reactivity of ADS-burner core.

Targets with actinides will be irradiated in the fast (і 0.1 MeV) and resonance-thermal (0.1 - 100 keV) neutron spectra. The experimental reactor targets will be developed to form the necessary neutron spectrum in the SM channels. Small amounts of actinides will be irradiated to minimize the effect of nuclei self-shielding.

Radiometry, mass spectrometry and other precision methods will be used for analysis of irradiated actinide samples. Based on the experimental data the integral neutron reaction rates for inpidual actinides will be determined.

In addition to the integrated experiments in the SM high-flux reactor and analysis of isotope composition of the actinide samples irradiated in the intermediate neutron spectrum, there will be made an analysis of the published experimental data on the nuclear-physical constants (first of all, total neutron cross-sections and resonance parameters) of actinides including those obtained with the SSC FR RIAR neutron selector.

The results of the reactor experiments will allow the development and verification of the more precise version of the nuclear-physical data library and verification of the calculating codes for the ADS-burner validation.

Moreover, an attempt will be made to integrate data on the behavior of actinides and fission products in molten fluorides and to gain fundamental data on the distribution of actinides (Np, Pu, Am, Cm) and basic FP in the molten fluoride salt – liquid metal phase (cadmium, bismuth, lead) system, on the effect of the joint presence of actinides and fission products on solubility of inpidual actinides in fluoride molten salts. The fundamental data of this sort are extremely important for justification of the operation and the fuel cycle concept of the ADS MSR-burner.