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Contribution of the JRC to the development of neutron resonance densitometry to characterize melted fuel from severe accidents

溶融燃料の核物質測定のための中性子共鳴濃度分析法に対するJRCの貢献

Schillebeeckx, P.*; Becker, B.*; Emiliani, F.*; Kopecky, S.*; Kauwenberghs, K.*; Moens, A.*; Mondelaers, W.*; Sibbens, G.*; 原田 秀郎 ; 北谷 文人; 小泉 光生; 呉田 昌俊; 飯村 秀紀; 高峰 潤; 土屋 晴文; Abousahl, S.*; Moxon, M.*

Schillebeeckx, P.*; Becker, B.*; Emiliani, F.*; Kopecky, S.*; Kauwenberghs, K.*; Moens, A.*; Mondelaers, W.*; Sibbens, G.*; Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Kureta, Masatoshi; Iimura, Hideki; Takamine, Jun; Tsuchiya, Harufumi; Abousahl, S.*; Moxon, M.*

JAEA and EC-JRC started a collaboration to study Neutron Resonance Densitometry (NRD) as a method for the characterization of melted fuel formed in nuclear accidents. NRD is based on a combination of Neutron Resonance Transmission Analysis (NRTA) and Neutron Resonance Capture Analysis (NRCA). In this presentation, the contribution of the EC-JRC-IRMM to the project is discussed. Within the project the GELINA facility will be used to validate the method and perform tests on calibration and test samples. In a first exercise the test samples will not contain actinides, however, they will contain nuclides having similar characteristics as the melted fuel for NRCA and NRTA. These samples will be produced and characterized at dedicated laboratories of our institute. To study the impact of the sample characteristics, in particular the particle size distribution of powder samples, various analytic models are compared. In addition stochastic simulations are used to select a specific model and to estimate the uncertainties introduced by the model. The stochastic model is also used to verify bias effects due to sample properties. The results of the simulations are verified by measurements at GELINA. In addition, the data reduction and analysis procedures will be adapted such that they can be used for in-field application of NRD. The changes required for NRD applications are discussed.

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