Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Ishikawa, Fumitaka; Abe, Tomoyuki; Chiba, Masahiko; Suzuki, Toru; Kuno, Yusuke; Sumi, Mika
no journal, ,
The accountancy analysis of the nuclear fuel material at Plutonium Fuel Development Center of JAEA is performed by isotope dilution mass spectrometry (IDMS). The standard material which called LSD spike is always required for IDMS and indispensable for the facilities where the nuclear fuel material is handled. However, the LSD spike and Pu material has been supplied from foreign countries and those transportation is becoming more difficult recently. The trend of an overseas supply may influence the facilities operation at JAEA in the future. Therefore, research and development of the domestic LSD spike and base material has been performed at JAEA. This report presents the current state and the future plan for the technological development.
Sumi, Mika; Takamatsu, Mai*; Ebisawa, Noriyuki; Abe, Katsuo; Kageyama, Tomio; Chiba, Masahiko; Nakazawa, Hiroaki; Suzuki, Toru; Katchi, Tomokazu*; Kushigeta, Yoshiyuki*; et al.
no journal, ,
Standard material which called Large Size Dried (LSD) spikes is required for Plutonium and Uranium measurement by Isotope Dilution Mass Spectrometry (IDMS). Collaboration work between JAEA and JNFL is performed to validate efficient use of standard material (primary) and to evaluate the effectivity of the Pu which separated and purified from MOX stored at JAEA. According to the presentation "Preparation and evaluation of reference materials (LSD spikes) (1) Preparation and testing", uncertainty of the actual sample measurements at Rokkasho Reprocessing plant are evaluated with GUM. Also, the effectivity of the half sized LSD spikes from generally used at JAEA and LSD spikes which prepared from Pu purified from MOX at JAEA are statistically evaluated and validated.
Katchi, Tomokazu*; Kushigeta, Yoshiyuki*; Murakami, Yoshiki*; Hishi, Tomoyuki*; Ai, Hironobu*; Takamatsu, Mai*; Ebisawa, Noriyuki; Sumi, Mika; Abe, Katsuo; Kageyama, Tomio; et al.
no journal, ,
Standard material which called Large Size Dried (LSD) spikes is required for Plutonium and Uranium measurement by Isotope Dilution Mass Spectrometry (IDMS). Collaboration work between JAEA and JNFL is performed to validate efficient use of standard material (primary) and to evaluate the effectivity of the Pu which separated and purified from MOX stored at JAEA. Preparation of the LSD spikes at JAEA and evaluation with actual samples with remote operation systems at JNFL will be presented.
Nakase, Masahiko*; Chiba, Go; Saito, Masaki*
no journal, ,
Higher-order eigenvalues can be useful indices for reactor core stability. Usually, higher-order eiganvalues are calculated with the subtraction method in which several numerical techniques are necessary. In this present study, we develop a simple method to estimate higher-order eigenvalues from a residual of power iteration. Through numerical calculations with the IAEA benchmark problem, the present method estimates higher-order eigenvalues up to the 5th order quite well.
Asano, Hidekazu*; Sakuragi, Tomofumi*; Hamada, Ryo*; Han, C. Y.*; Nakase, Masahiko*; Matsumura, Tatsuro; Chiba, Go*; Sagara, Hiroshi*; Takeshita, Kenji*
no journal, ,
no abstracts in English
Matsumura, Tatsuro; Asano, Hidekazu*; Sakuragi, Tomofumi*; Hamada, Ryo*; Han, C. Y.*; Nakase, Masahiko*; Chiba, Go*; Sagara, Hiroshi*; Takeshita, Kenji*
no journal, ,
The issue of high-level waste disposal is important for the sustainable use of nuclear energy. P&T technology of long-lived and highly radiotoxic MA is a key technology. The MA separation process, which separates MA from the high-level waste, is one of the essential technology for realizing the P&T technology. JAEA has been developing the SELECT process using the solvent extraction technique for the MA separation process. Target values for separation performance were 99% recovery rate based on radiotoxicity evaluation and 95% MA product purity from evaluation of the performance of transmutation system. The separation process was demonstrated by the test using genuine HLW. SELECT process consists of two steps. The second step for MA/RE separation requires 40 extraction stages for the target value, and there was a issue of introduction and operation costs. Therefore, we set a reasonable recovery rate based on the evaluation of the environmental impact of the disposal site. Based on the target value, quantitative evaluation was carried out using the PARC-MA code, and the number of extraction stages in the MA/RE separation process and the purity of the MA product were obtained. We believe that the configuration of a realistic simplified MA separation process has been clarified.
Asano, Hidekazu*; Sakuragi, Tomofumi*; Hamada, Ryo*; Han, C. Y.*; Nakase, Masahiko*; Matsumura, Tatsuro; Chiba, Go*; Sagara, Hiroshi*; Takeshita, Kenji*
no journal, ,
no abstracts in English