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Oral presentation

Radiation monitoring via manned helicopter

Futemma, Akira

no journal, , 

no abstracts in English

Oral presentation

Outline of the Emergency Preparedness Research Group and evaluation for utilization of radiation portal monitors in contamination inspection in nuclear emergency

Hiraoka, Hirokazu

no journal, , 

The author reports the outline of Emergency Preparedness Research Group and one of its research results. Utilization of radiation portal monitors are being considered for contamination inspection in nuclear emergency. In this study, the practicality of the monitor was evaluated experimentally for its utilization. It was found that contamination on the tire surface equivalent to OIL4, one of the Operational Intervention Levels (OILs), could be detected sufficiently. However, it was found that it was difficult to determine whether contamination on the tire surface and wiper areas was above or below OIL4.

Oral presentation

Developments of two-phase flow measurement systems with various techniques

Hirose, Yoshiyasu

no journal, , 

no abstracts in English

Oral presentation

Development of adjoint-weighted k-eigenvalue sensitivity coefficient capability in Solomon solver

Tuya, D.

no journal, , 

A new continuous-energy neutron transport Monte Carlo solver Solomon is under development at JAEA. The Solomon solver has a distinct capability of calculating criticality of continuously-varying random media expressed with randomized Weierstrass function. One important feature of any Monte Carlo transport code is a capability for sensitivity/uncertainty analysis. This presentation discusses the development of k-eigenvalue sensitivity coefficient capability for the Solomon solver.

Oral presentation

Overview of research activities of the Fuel Safety Research Group

Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori; Kakiuchi, Kazuo; Tasaki, Yudai; Udagawa, Yutaka

no journal, , 

no abstracts in English

Oral presentation

The Overview of research on Materials Evaluation Research Group and a study on the structural integrity assessment of reactor pressure vessels

Hata, Kuniki; Iwata, Keiko; Shimodaira, Masaki; Ha, Yoosung; Takamizawa, Hisashi; Katsuyama, Jinya

no journal, , 

no abstracts in English

Oral presentation

Research outline of the Criticality Safety Research Group

Gunji, Satoshi; Watanabe, Tomoaki; Suyama, Kenya; Araki, Shohei; Fukuda, Kodai

no journal, , 

The criticality safety research group had been conducted research using deterministic methods to ensure the criticality safety. However, the retrieval work of fuel debris in the Fukushima Dai-ichi Nuclear Power Station cannot be evaluated by the conventional criticality management methods, therefore it is necessary to develop a risk-informed control method. In this presentation, among the research activities undertaken to address these research issues, the following research topics are presented. (1) Criticality Map Database, (2) Support for the new STACY installation and certification, (3) Study of the new STACY experiments, (4) Post-Irradiation Examination (PIE) / Combustion Analysis

Oral presentation

Evaluation of mechanical properties of fuel cladding tubes using nanoindentation

Kakiuchi, Kazuo; Yamauchi, Akihiro*

no journal, , 

no abstracts in English

Oral presentation

Advancement of structural integrity assessment of nuclear reactor components considering age-related degradation

Yamaguchi, Yoshihito; Takamizawa, Hisashi; Mano, Akihiro; Li, Y.

no journal, , 

no abstracts in English

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