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Journal Articles

Preliminary analyses of modified STACY core configuration using serpent with JENDL-5

Kawaguchi, Maho*; Shiba, Shigeki*; Iwahashi, Daiki*; Okawa, Tsuyoshi*; Gunji, Satoshi; Izawa, Kazuhiko; Suyama, Kenya

Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 8 Pages, 2023/10

The Nuclear Regulation Authority (NRA) has been working on an experimental approach for evaluating the criticality of fuel debris produced by the Fukushima Daiichi Nuclear Power Plant (FDNP) accident since 2014, collaborating with the Japan Atomic Energy Agency (JAEA). As part of the approach, JAEA has modified the STAtic experiment Critical facilitY (STACY) for critical experiments to evaluate characteriscs of pseudo-fuel debris. As the preliminary analyses, we verified critical characteristics with major nuclear data libraries for the proposed core configuration patterns. The three-dimensional continuous-energy Monte Carlo neutron and photon transport code, SERPENT-V2.2.0 was used with the latest JENDL, JENDL-5. As a result, larger multiplication factors of JENDL-5 across the modified STACY core configuration patterns were evaluated in comparison to the other libraries. And, $$^{1}$$H scattering and $$^{238}$$U fission sensitivity coefficients of JENDL-5 were different from those of the other libraries. Comparing among analyses with those libraries, the updated S($$alpha$$, $$beta$$) of JENDL-5 might affect the result of critical characteristics in the critical analyses for the modified STACY core configuration.

Journal Articles

Preliminary analysis of randomized configuration patterns in modified STACY core

Shiba, Shigeki*; Iwahashi, Daiki*; Okawa, Tsuyoshi*; Gunji, Satoshi; Izawa, Kazuhiko; Suyama, Kenya

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 9 Pages, 2023/05

The Nuclear Regulation Authority (NRA) has tackled the experimental approach for determining the criticality of pseudo-fuel debris plausibly simulating actual fuel debris since 2014, collaborating with the Japan Atomic Energy Agency. To elucidate the characteristics of the pseudo-fuel debris, the Japan Atomic Energy Agency modified the STACY (STAtic experiment Critical facilitY) to conduct critical experiments simulating fuel debris. Thus, we proposed three types of modified STACY core configurations. In critical experiments in the modified STACY core, it is important to judge whether the proposed modified STACY core configurations are representative of molten core-concrete interaction debris or not. In this study, we built pseudo-fuel debris models considering a volume ratio of pseudo-fuel debris to moderation (V$$_{m}$$/V$$_{f}$$) and calculated uncertainty-based similarity values (C$$_k$$) between the modified STACY core configurations and pseudo-fuel debris models using Tools for Sensitivity and Uncertainty Analysis Methodology Implementation-Indices and Parameters (TSUNAMI-IP) in SCALE 6.2. Consequently, the modified STACY core configuration loading structure rods we proposed completely resulted in high similarity to the pseudo-fuel debris models through V$$_m$$/V$$_f$$ values. The main contributions to C$$_k$$ values were $$^{235}$$U $$bar{nu}$$, $$^{235}$$U $$chi$$, and $$^{56}$$Fe (n,$$gamma$$), except for the pseudo-fuel debris model, including extremely high concrete components.

Oral presentation

Medical RI production in existing reactors, 1; Ac-225 production in the core center/reflector region of the experimental fast reactor Joyo

Iwahashi, Daiki*; Sasaki, Yuto*; Maeda, Shigetaka; Takaki, Naoyuki*

no journal, , 

Ac-225 is attracting attention as a radioisotope for targeted $$alpha$$-therapy (TAT) used for the treatment of prostate cancer and the like. Therefore, we investigated a method of loading Ra-226 into the fast reactor Joyo and producing Ac-225 by transmutation. Ac-225 production can be expected by the (n,2n) reaction using fast neutrons in the center of the core and the (3n,$$alpha$$$$beta$$) reaction using thermalized neutrons in the reflector region.

Oral presentation

Medical RI production in existing reactors, 2; Optimization of neutron spectrum field for Mo/Tc production in the experimental fast reactor Joyo

Sasaki, Yuto*; Iwahashi, Daiki*; Maeda, Shigetaka; Takaki, Naoyuki*

no journal, , 

Mo-99 (half-life: 66 hours) / Tc-99m (half-life: 6 hours), which is the most sought after RI for diagnosis, is 100% dependent on imports. Therefore, domestic production is expected due to the instability of supply due to the deterioration of overseas manufacturing reactors and transportation troubles caused by natural disasters, and discussions are becoming active in the RI expert subcommittee. In this study, we investigated a method for efficiently producing Mo-99 by the neutron capture reaction of Mo-98 utilizing the neutron deceleration field around the core of the high-speed experimental reactor "Joyo". Specifically, a parameter survey was conducted on the core configuration, target loading position, deceleration aggregate material and its filling ratio, etc., and the most efficient core configuration was clarified.

Oral presentation

Medical RI production in existing reactors, 3; Comparison of medical RI production performances in Joyo and PWR

Takaki, Naoyuki*; Iwahashi, Daiki*; Sasaki, Yuto*; Maeda, Shigetaka

no journal, , 

We compared the production characteristics of Tc-99m and Ac-225 in the fast experimental reactor "Joyo" and commercial PWR, summarized the characteristics of each, and showed the possibility of domestic production of medical RI using domestic infrastructure.

Oral presentation

Domestic production of Mo-99 and Ac-225 using commercial PWR and fast experimental reactor Joyo

Takaki, Naoyuki*; Iwahashi, Daiki*; Sasaki, Yuto*; Maeda, Shigetaka

no journal, , 

The production technology of medical radioisotopes (RI) using existing nuclear fission reactors has been studied to improve/achieve their domestic preparedness in Japan. The target nuclides currently considered in our project are Mo/Tc which is the most commonly used ones in medical diagnosis and Ac-225 which is recently known as effective alpha emitting nuclide for targeted alpha-particle therapy. Existing fission reactors, PWRs and Joyo, have potentials to work as excellent facilities for medical isotope production, as by-products of heat/electricity generation without consuming electricity and need for new plant construction.

Oral presentation

Evaluation of $$^{225}$$Ac production rate and its uncertainty in the experimental fast reactor Joyo utilizing the total Monte Carlo method

Sasaki, Yuto; Iwahashi, Daiki*; Maeda, Shigetaka; Takaki, Naoyuki*

no journal, , 

Ac-225 is attracting attention as an alpha emitting medical radioisotope. Since its demand is expected to increase, domestic production of Ac-225 is required from the viewpoint of medical research and economic security of Japan. To establish the technical bases for the Ac-225 production, JAEA has evaluated the radioactivity can be produced in the experimental fast reactor Joyo and designed the concept that upgrades the existing facilities for transporting the irradiated target from Joyo to a neighboring PIE facility rapidly. This study has revealed that Joyo can sufficiently produce Ac-225 as a raw material for pharmaceuticals.

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