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Benchmark Data on Gamma-ray Production for Fusion Reactors

#0731


Benchmark Data on Gamma-ray Production for Evaluated Data Testing for Fusion Application

Tech Area / Field

  • FUS-OTH/Other/Fusion

Status
8 Project completed

Registration date
27.08.1996

Completion date
10.04.2002

Senior Project Manager
Hamada S

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

Supporting institutes

  • VNIIEF, Russia, N. Novgorod reg., Sarov

Collaborators

  • JAERI / Tokai Research Establishment, Japan, Tokai Mura

Project summary

The objective of the project is the measurement and evaluation of benchmark data on gamma-ray production in fast neutron induced reactions for materials most important in developing of fusion power reactors. Such data are needed to test and to improve the recommended neutron cross sections included in the national evaluated neutron data libraries ENDF/B-VI, JENDL-3, EFF-2, BROND-2 and the international library FENDL specially prepared for fusion applications.

Expected Results


1. Development of experimental methods and precise measurements of gamma-ray production cross-sections for the neutron induced reactions, improvement of codes for the experimental data analysis and uncertainty estimation.
2. New experimental data on gamma-ray production cross-sections and gamma-ray spectra for the 14 MeV incident neutrons on the following nuclei: 6Li, 7Li, 10B, 11B, С, N, О, Na, Mg, Al, Si, S, Cl, Ti, V, Cr, Fe, Ni, Cu, Zn, Ge, Zr, Nb, Mo, Cd, In, Sn, Dy, W, Pb, Bi, 235U, 238U and 239Pu.
3. All experimental data obtained will be compared with evaluated data available in different national and international data libraries. New evaluations will be performed for isotopes where essential contradictions new and old data will be found.
4. The library of new benchmark data important for a crucial test of gamma-ray production in fusion power reactors will be prepared and described in details.

Commercial Efficiency

The more accurate nuclear data permit to avoid many design uncertainties and reduce essentially expenses on initial stages of fusion technology development. A reduction of design uncertainties has crucial importance for a choice of most safe and effective scenario of a future development of nuclear power industry.

Potential Role of Foreign Collaborators

Needs on nuclear data for gamma-ray production in the neutron induced reactions are reflected in the conclusions of the IAEA Advisory Group Meetings on "FENDL-2 and Associated Benchmark Calculations" (Vienna, November 1991) and on "Improved Evaluations and Integral Data Testing for FENDL" (Garching, September 1994). The interest to such data was expressed by experts from JAERI (Japan), ANL (USA), CEA (France), KFK (Germany) and ENEA (Italy). Any collaboration with these nuclear centers and other interested organizations directed on improvement of nuclear data on the gamma-ray production will be welcomed.


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