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Journal Articles

Isotope dilution inductively coupled plasma mass spectrometry for determination of $$^{126}$$Sn content in spent nuclear fuel sample

Asai, Shiho; Toshimitsu, Masaaki; Hanzawa, Yukiko; Suzuki, Hideya; Shinohara, Nobuo; Inagawa, Jun; Okumura, Keisuke; Hotoku, Shinobu; Kimura, Takaumi; Suzuki, Kensuke*; et al.

Journal of Nuclear Science and Technology, 50(6), p.556 - 562, 2013/06

 Times Cited Count:11 Percentile:64.36(Nuclear Science & Technology)

The $$^{126}$$Sn content in a spent nuclear fuel solution was determined by ICP-MS for its inventory estimation in high-level radioactive waste. An irradiated UO$$_{2}$$ fuel was used as a sample to evaluate the reliability of the methodology. Prior to the measurement, Sn was separated from $$^{126}$$Te, which causes major isobaric interference in the determination of $$^{126}$$Sn content, along with highly radioactive coexisting elements using an anion-exchange column. The absence of counts attributed to Te in the Sn-containing effluent indicates that Te was completely removed. After washing, Sn retained on the column was readily eluted with 1 M HNO$$_{3}$$. The isotope ratios of Sn were successfully determined and showed good agreement with those obtained through ORIGEN2 calculations. The results reported in this paper are the first experimental values of $$^{126}$$Sn content in the spent nuclear fuel solution originating in spent nuclear fuel irradiated at a nuclear power plant in Japan.

Journal Articles

Development of "leaky" liposome triggered by radiation applicable to a drug reservoir and a simple radiation dosimeter

Akamatsu, Ken

Applied Radiation and Isotopes, 74, p.144 - 151, 2013/04

 Times Cited Count:3 Percentile:25.83(Chemistry, Inorganic & Nuclear)

Effects of lipid compositions and the content ratios on the membrane permeability of liposome have been investigated using soft X-rays as ionizing radiation (IR) sources. Three-component liposome constituted from an unsaturated phosphatidyl choline (PC), a saturated PC, and cholesterol was selected in a series of the study. As the results, following characteristics of IR-sensitive liposome were discovered: (1) A PC with bis-allylic hydrogen is essential as a component of unsaturated PC., (2) Dilinoleoyl PC (DLOPC) is optimal as a component of unsaturated PC., (3) Either distearoyl PC (DSPC) or dipalmitoyl PC (DPPC) is optimal as a component of saturated PC., (4) Lower dose- rate makes the liposome more IR-sensitive., (5) Lower concentration of liposome makes the liposome more IR-sensitive., (6) There is a region for optimal DLOPC content ratio for the IR-sensitive liposome around 5 $$sim$$ 20 mol%., and (7) There is a region for optimal cholesterol content ratio for preparing a stable liposome around 30 $$sim$$ 60 mol%. These fundamental laws for IR-sensitive liposome will contribute to understanding of biomembrane damage by IRs and developing a new-conceptual pharmaceutical available in radiotherapies.

Journal Articles

Computational study for inventory estimation of Se-79, Tc-99, Sn-126, and Cs-135 in high-level radioactive wastes from spent nuclear fuels of light water reactors

Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Okamoto, Tsutomu; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Kimura, Takaumi; Suzuki, Kensuke*; Kaneko, Satoru*

Proceedings of 14th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2011) (CD-ROM), p.1443 - 1450, 2011/09

Inventory estimation of long-lived fission products (LLFPs) in high-level radioactive wastes (HLW) from spent nuclear fuels of light water reactors is important for a safety assessment of their disposal. In order to develop an inventory estimation method of difficult-to-measure LLFPs (Se-79, Tc-99, Sn-126, and Cs-135), a parametric study was carried out by using a sophisticated burnup calculation code and data. In the parametric study, fuel specifications and irradiation conditions are changed in the conceivable range. The considered parameters are fuel assembly types (PWR / BWR), U-235 enrichment, moderator temperature, void fraction, power density, and so on. From the calculated results, we clarify the burnup characteristics of the target LLFPs and their possible ranges of generations. Finally, candidates of the key nuclide are proposed for the scaling factor method of HLW.

Journal Articles

Comparison of post-irradiation experimental data and theoretical calculations for inventory estimation of long-lived fission products in spent nuclear fuel

Asai, Shiho; Hanzawa, Yukiko; Okumura, Keisuke; Suzuki, Hideya; Toshimitsu, Masaaki; Shinohara, Nobuo; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.261 - 264, 2010/10

JAEA Reports

Fuel irradiation research of Japan at Halden reactor; Achievement of cooperative researches between JAERI and several organizations in the period from 2000 to 2002 (Joint research)

Committee of the Halden Joint Research Programme

JAERI-Tech 2004-023, 38 Pages, 2004/03

JAERI-Tech-2004-023.pdf:1.85MB

JAERI has performed cooperative researches with several Japanese organizations utilizing the Halden Boiling Heavy Water Reactor(HBWR) which is located at Halden in Norway. These researches are carried out based on the contracts of the cooperative researches, which are revised every three years, in accordance with the renewal of the participation of JAERI to the OECD Halden Reactor Project. This report summarizes the objectives, contents and the outlines of the achievements of the cooperative researches during the three years from 2000 January to 2002 December. During the period, seven cooperative researches had been carried out. Two of them had been completed and other five researches have been continued to the next three years period. Most of them are irradiation test researches of advanced fuel and cladding in order to prepare the higher burnup utilization and introduction of LWR fuel and MOX fuel in LWRs of Japan.

JAEA Reports

None

Kawamura, Katsuyuki*; Ichikawa, Yasuaki*; Suzuki, Satoru; Shibata, Masahiro; Sato, Haruo; Ueno, Kenichi

JNC TY8400 2002-015, 90 Pages, 2002/03

JNC-TY8400-2002-015.pdf:26.99MB

None

Oral presentation

O(1s) photodissociation dynamics of gas-phase H$$_2$$O

Harries, J.; Gejo, Tatsuo*; Kuniwake, Miki*; Homma, Kenji*; Oura, Masaki*; Sullivan, J. P.*; Azuma, Yoshiro*

no journal, , 

Photo-excitation of the O 1s electron in H$$_2$$O can lead to the production of neutral, excited H atoms. Knowledge of the excited state distribution provides information on the dissociation dynamics process. Excitation of the O 1s electron leads to a H$$_2$$O$$^+$$ ion core. Auger decay subsequently leads to H$$_2$$O$$^{2+}$$, which dissociates, and one of the fragments can capture the initially excited electron. If this fragment is H$$^+$$, excited neutral H atoms are formed. In this research we use pulsed synchrotron radiation as the excitation source, and detect the UV fluorescence emitted when the excited H atoms decay. Analysis of the decay lifetimes leads to information on the excited state distribution.

Oral presentation

Determination of long-lived radionuclide in spent nuclear fuel; Simple and rapid sample preparation for determination of $$^{79}$$Se

Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Okumura, Keisuke; Shinohara, Nobuo; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

no journal, , 

no abstracts in English

Oral presentation

Influence of differences between seismic safety evaluation methods for equipment and piping of a nuclear facility

Nishida, Akemi; Iigaki, Kazuhiko; Sawa, Kazuhiro

no journal, , 

The objective of this research was to investigate the influence of differences between methods for evaluating the seismic response of the equipment and piping of a nuclear facility. For the input ground motion, one wave was chosen from among 200 waves of input ground motions of maximum acceleration of 700-1100 cm/s$$^{2}$$ created for the Oarai District of the Ibaraki Prefecture. Seismic safety evaluations were performed using the conventional method, which relies on floor response spectrum data, the multi-input method, and the analytical method using a three-dimensional building model. The differences between the three methods were summarized. The target equipment and piping system were cooling systems in a model plant. It was found that the response predicted by the multi-input method and the analytical method using three-dimensional building model were approximately half of the response predicted by the conventional method.

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