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Actinides Transmutation Study at Critical Assembly

#2582


Experimental Study of Minor Actinides Transmutation Problem at BFS-73-1 Fast Critical Assembly

Tech Area / Field

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

Status
8 Project completed

Registration date
07.08.2002

Completion date
17.02.2006

Senior Project Manager
Kulikov G G

Leading Institute
FEI (IPPE), Russia, Kaluga reg., Obninsk

Collaborators

  • Idaho National Engineering and Environmental Laboratory, USA, ID, Idaho Falls\nKorea Atomic Energy Research Institute (KAERI), Korea, Yuseong

Project summary

The aim of the project is experimental and calculational investigation of minor actinides (MA) transmutation possibilities in a fast reactor with a metal uranium fuel taking into consideration modern status of nuclear data, calculating codes and methods.

This aim is agreed with ISTC tasks in support of applied investigations directed to peaceful fast reactors application for ecologically acceptable fuel cycle.

The effectiveness of MA transmutation depends on different physical conditions in which they can be placed. One of the possible variants of such conditions is a metal uranium fast reactor core that has been studied at BFS-73-1 critical assembly. The experiments at the assembly have been implemented according to Russian program of MA transmutation studies in fast reactors. They included measurements of fission cross-sections ratios of Np-237, Am-241 and Am-243 to Pu-239 fission., capture cross-section of Np-237 to Pu-239 fission and central reactivity worth of Np-237 samples normalized to U-235 or Pu-239. These parameters are determined using different kinds of fission chambers, activation detectors and core perturbation samples, so, that several techniques can be and will be applied to derive them from the acquired experimental data. The analysis is carried out taking into consideration fission cross-sections ratios and reactivity coefficients of typical neutron absorbers and scattering materials.

Different experimental methods used provide a reliability and consistency of the obtained data decreasing their uncertainties. Both experimental and derivation methods will be described as attachments to the experimental data.

The experimental information will be analyzed on the basis of all relevant evaluation methods and codes used at IPPE.

Recommendations on the studied MA neutron data on the basis of the experimental results, on uncertainty decrease of calculation parameters due to the testing will be done for the central spectral region of the core.

It is expected to generate the experiments benchmark models valid for calculation codes and neutron data verification, to evaluate their uncertainties and influence on the measured parameters.

The whole work is subpided on the two directions:

– Task 1 will be devoted to description of the carried out experiments and used tools;


– Task 2 will be connected with the experiments evaluation.


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