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Journal Articles

Phenix to Monju; FBR development and Japan role, 1; Incident in development of FBR and its effect on the development

Konomura, Mamoru

Nippon Genshiryoku Gakkai-Shi, 53(3), p.211 - 214, 2011/03

It is not too much to say that R&D people have common sense to manage incidents in development of FBR with a method of risk analysis. In order to avoid an accident from some incidents, a reactor plant is designed with a way of defense in depth and a concept of multiple function and diversity in the design phase and is constructed and operated with enhancement of its reliability. Actually it is impossible to avoid any mechanical incidents. But the reliability can be enhanced by these incidents with appropriate risk management. In this sense, incidents are valuable for development of FBR. We should pay attention to developer's attitude how he understand incidents and how he improve his system on condition that he keeps transparency of information to public.

Oral presentation

A Study on evaluation method of stress corrosion cracking progress

Watanabe, Masatoshi; Takeda, Seiji; Maeda, Toshikatsu

no journal, , 

no abstracts in English

Oral presentation

Study on uncertainty of soil-to-plant transfer factor for the safety assessment

Saito, Hironori; Takeda, Seiji; Kimura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Basic design models for estimation of effect on host rock caused by geological and climate events

Nagasawa, Hirokazu; Takeda, Seiji; Sakai, Ryutaro; Kimura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Development of fuel handling system in FaCT project, 5; Cooling performance of MA bearing fresh fuel shipping cask

Chikazawa, Yoshitaka; Kato, Atsushi; Obata, Hiroyuki*

no journal, , 

no abstracts in English

Oral presentation

Dissolution of simulated high-level waste glass in silica-saturated solution at a wide range of pH

Maeda, Toshikatsu; Hotta, Katsutoshi*; Usui, Hideo

no journal, , 

no abstracts in English

Oral presentation

Solubility of selenium at high ionic strength under anoxic conditions

Iida, Yoshihisa; Yamaguchi, Tetsuji; Tanaka, Tadao; Nakayama, Shinichi

no journal, , 

Solubility experiments for selenium were performed at high ionic strengths under anoxic conditions. Dominant aqueous selenium species were identified as hydrogen selenide at pH between 5 and 8, and polyselenide at pH between 9 and 13 by UV-Vis absorption spectrometry. A solubility-limiting solid was determined to be amorphous selenium at pH between 5 and 8, and crystalline selenium at pH between 9 and 13. The equilibrium constants and ion interaction coefficients for HSe- and Se42- versus Na+ were determined by specific ion interaction theory.

Oral presentation

Development of fuel handling system in FaCT project, 4; Evaluation of residual sodium on spent fuel subassembly after cleaning

Obata, Hiroyuki

no journal, , 

We evaluated the amount of the residual sodium on the fuel assembly by using the results of the dry cleaning tests of the fuel assembly mockup. We report the results of the dry cleaning test and the evaluation of the residual sodium on the assembly.

Oral presentation

Study on transient behavior of research reactor fuel; Influence of fuel core density

Yanagisawa, Kazuaki

no journal, , 

An influence of fuel core density (2.2, 3.0 and 4.0g/cc) on a fuel failure was studied comparing the silicide fuel (4.8 g/cc) as the reference. (1) The DNB value of the test specimens (below 4.8g/cc) was 175$$pm$$24$$^{circ}$$C, having no difference to the reference (180$$pm$$14 $$^{circ}$$C). (2) The reference fuel failed at the large temperature drop (larger than 94 $$^{circ}$$C) and the short time to quench (shorter than 0.13s). The test specimens did not fail until 106 cal/g per fuel plate due to the enhanced plasticity of the aluminum matrix. The lower the fuel density, the more the plasticity enhanced. (3) Irrespective to fuel density, the bow was increased with the increasing PCST. Experimental fact revealed that maximum bow at JRR 3 operating (lower than 228 $$^{circ}$$C) is 15% (0.4 mm), where the almost data are within 4% (0.1 mm). (4) For axial permanent strain evaluated by the plate thickness, the test specimens were expanded but the references were shrunk.

Oral presentation

Development of an atmosphere-vegetation-soil HTO transport and OBT production model

Ota, Masakazu; Nagai, Haruyasu

no journal, , 

no abstracts in English

Oral presentation

A Numerical simulation of atmospheric dispersion of $$^{85}$$Kr released from the Rokkasho Reprocessing Plant by an atmospheric dispersion model in SPEEDI-MP

Terada, Hiroaki; Nagai, Haruyasu; Isogai, Keisuke*; Nitta, Wataru*

no journal, , 

We have been verifying and improving SPEEDI-MP which is a comprehensive prediction system of migration of radionuclides in the atmosphere, ocean, and terrestrial region. In this study, we conducted atmospheric dispersion simulations of radioactive noble gas $$^{85}$$Kr released from the Rokkasho reprocessing plant for the whole Japan area by using an atmospheric model in SPEEDI-MP, and analyzed significant increases of atmospheric $$^{85}$$Kr concentration above its background level measured by Japan Chemical Analysis Center. Meteorological fields such as wind field and turbulence were predicted by an atmospheric dynamic model MM5, and atmospheric dispersion of $$^{85}$$Kr was calculated by a Lagrangian particle dispersion model GEARN. The calculation results agreed well with the measurements of atmospheric $$^{85}$$Kr concentration at Dazaifu in April 2008 and at Sapporo in September 2008 to confirm the high prediction performance of the model.

Oral presentation

Feasibility study on phosphate ester fluid treatment by steam reforming

Aoyama, Yoshio; Nakagawa, Akinori; Sone, Tomoyuki; Sasaki, Toshiki; Nakazawa, Osamu; Tashiro, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Fission fragment mass distributions for actinide nuclei produced by nucleon transfer reaction

Nishio, Katsuhisa; Nishinaka, Ichiro; Mitsuoka, Shinichi; Makii, Hiroyuki; Furutaka, Kazuyoshi; Wakabayashi, Yasuo; Takahashi, Ryuta*; Ishii, Tetsuro; Chiba, Satoshi; Hirose, Kentaro*; et al.

no journal, , 

no abstracts in English

Oral presentation

Analysis of fission-process of compound nucleus produced by surrogate reaction

Aritomo, Yoshihiro; Chiba, Satoshi; Nishio, Katsuhisa

no journal, , 

no abstracts in English

Oral presentation

Present status and future plan of the collaboration with Russia concerning vipac fuel

Funada, Toshio; Suzuki, Mitsutoshi; Senzaki, Masao

no journal, , 

The outline of the collaboration concerning to the plutonium disposition with Russian institutes on vipac fuels and the future plan will be presented in the conference. (one of the four series presentations)

Oral presentation

Oral presentation

Verification of detailed two-phase flow simulation code TPFIT to water jet, 5; Modification of surface tension force model

Yoshida, Hiroyuki; Suzuki, Takayuki*; Takase, Kazuyuki; Koizumi, Yasuo*

no journal, , 

no abstracts in English

Oral presentation

Technical development on immobilization/solidification of waste salt arising from pyroprocessing, 1; Fundamental study on applicability of use of iron phosphate glass as waste form

Amamoto, Ippei; Fukushima, Mineo; Matsuyama, Kanae*; Okita, Takeshi*; Miyamoto, Shinya*; Utsunomiya, Kazuhiro*; Yano, Tetsuji*

no journal, , 

no abstracts in English

Oral presentation

Verification of detailed two-phase flow simulation code TPFIT to water Jet, 4; Water experiment on high flow velocity condition

Ikuta, Ryuhei*; Koizumi, Yasuo*; Takase, Kazuyuki

no journal, , 

no abstracts in English

Oral presentation

Microscopic statistical nuclear level density with the Skyrme-Hartree-Fock method

Minato, Futoshi

no journal, , 

no abstracts in English

364 (Records 1-20 displayed on this page)