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JAEA Reports

Survey on the planning process for waste characterization with statistical methods; Data quality objectives process

Murakami, Masashi; Sasaki, Toshiki

JAEA-Review 2022-004, 106 Pages, 2022/06

JAEA-Review-2022-004.pdf:3.95MB

A numerous analytical data will be required for the characterization of the radioactive waste stored in Japan Atomic Energy Agency toward their processing and disposal. A "Data Quality Objectives (DQO) Process" is widely applied as a tool for the development of a cost-effective characterization plan in the overseas nuclear sites. The DQO Process is a multi-step planning process developed by the United States Environmental Protection Agency (EPA), and can be used for the planning of a scientifically rigorous and cost-effective data collection program for the various projects involving the collection of the environmental data. We have considered to reduce the cost required for the future characterization of the stored waste by applying the statistical methods and have performed a literature survey on the DQO Process. The survey effort was focused on the guidance documents of the DQO Process published by the EPA and was also spent for the related matters such as a quality system of the EPA and the activities beyond the DQO Process as well as the examples of the application at the nuclear sites. In this report, the details on the planning procedure using the DQO Process are reviewed together with the background information such as why DQO Process was developed, what kind of transition was occurred, and how it is currently used in the EPA. The examples on the application for various objects at Hanford Site in the United States, where has the various legacy waste generated in the past activities and has the big environmental problems, are also reviewed. This report summarizes the important matters and methodology on the planning with the statistical sampling methods. It also provides the examples of the approaches for the complex objects, and will therefore be helpful in the future planning for the various kind of the waste characterization.

Journal Articles

Development of synthesis and morphology control method of metallic oxide particles using microwave heating

Segawa, Tomoomi

Funtai Kogakkai-Shi, 55(10), P. 547, 2018/10

no abstracts in English

Journal Articles

Necessity (proposal) of secure detection system of nuclear materials and interior inspection systems of detected / suspicious objects in non-destructive manner for safe dismantling

Seya, Michio; Hajima, Ryoichi*; Kureta, Masatoshi

Dai-37-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu (CD-ROM), 10 Pages, 2017/02

Large size freight cargo containers are the most volunurable items from nuclear security points of view because of their large volume and weight of cargo inside for hiding heavily shielded objects. For strengthning nuclear security, secure detection of NMs in heavily shielded objects, and safe handling (dismatlement) of detected / suspicious objects for taking out of NMs, are essential. These require the following things, (1) Introduction of secure detection system of NMs, (2) Inspection of deteiled and interior structures of detected objects, (3) Rough chracterization of NMs (for nuclear bomb or RDD etc.) / Confirmation of existence of explosives etc.. By using information obtained by interior inspections, safe dismantlement of objects and taking NMs out are possible. In this papaer, we propose a combined system of X-ray scanning system with NRF-based NDD system using monochromatic $$gamma$$-ray beam not only as a secure detection system of NMs but also interior inspection system (covering (1) and (2)). Also we propose active neutron NDA system using a D-T source for interior inspection of NM part (covering (3)).

JAEA Reports

Basic properties of the concrete using the low alkaline cement (HFSC) developed by JAEA

Seno, Yasuhiro*; Nakayama, Masashi; Sugita, Yutaka; Tanai, Kenji; Fujita, Tomoo

JAEA-Data/Code 2016-011, 164 Pages, 2016/11

JAEA-Data-Code-2016-011.pdf:8.45MB
JAEA-Data-Code-2016-011-appendix(CD-ROM).zip:0.1MB

The cementitious materials are used as candidate materials for the tunnel support of the deep geological repository of high-level radioactive wastes (HLW).Generally the pH of leachate from concrete mixed Ordinary Portland Cement (OPC) shows a range of 12 to 13. The barrier function of bentonite used as a buffer material and that of host rock might be damaged by the high alkaline leachate from cementitious materials. Therefore, low alkalinity that does not damage each barrier function is necessary for cementitious materials used for the tunnel support system of the HLW geological repository. JAEA has developed a low alkaline cement named as HFSC (Highly Fly-ash contained Silicafume Cement) which the pH of the cement leachate could lower approximately 11. We have confirmed the applicability of HFSC for the tunnel support materials, by using experimentally as the shotcreting materials to the part of gallery wall at 140m, 250m and 350m depth in Horonobe Underground Research Laboratory. And moreover, HFSC has been used as the cast-in-place concrete for the shaft lining concrete at the depth of 374m-380m. This Data/Code summarized the past HFSC mix proportion test results about the fresh concrete properties and hardened concrete properties, in order to offer the information as a reference for selecting the mix proportion of HFSC concrete adopted to the disposal galleries et al. in the future.

JAEA Reports

Study of the quality of vipac oxide fuel obtained by pyro-processing

Kakehi, Isao;

JNC TN9400 2000-054, 84 Pages, 2000/04

JNC-TN9400-2000-054.pdf:7.15MB

This report describes accomplishment of the study on the quality of vipac (vibro-packed) oxide fuel obtained by pyrochemical processing (molten salt electrolytic processing). This study is intended to contribute to the design study of the pyro-reprocessing-vipac fuel recycling system of oxide fuel. In this study, vibro-packing experiment has been conducted using granular U0$$_{2}$$ obtained by molten salt electrolytic processing (cold experiment). The oxide pyro process developed by Research lnstitute of Atomic Reactors (RIAR) is the method in which the sintered oxide is electrically deposited on the cathode at approximately 600$$^{circ}$$C. 0xide granules for vipac fuel are obtained by crushing the oxide deposited on the cathode. This process is also developed as recycle process because it is capable of FP separation. Also in Japan, this process is studied as one of the new FBR fuel recycling systems. ln this study, we made an effort to clarify the mechanisms of vibro-packing of the electrically obtained granules, which influence on the effective parameters of vibro-packing density and fuel particles size distribution in the fuel cladding in case of non-sphere particles of the granules. As a result of the study, smear density of 75% and almost uniform distribution of U0$$_{2}$$ particles have been taken in the experiment, and much knowledge for the improvement of the vibro-packing quality has been found. And the possibility of the smear density over 80% and the uniform distribution of U0$$_{2}$$ particles has been suggested in this study.

JAEA Reports

None

*; Akatsuka, Hiroshi*; *; Suzuki, Tatsuya*; *; *;

JNC TY9400 2000-009, 41 Pages, 2000/03

JNC-TY9400-2000-009.pdf:1.22MB

no abstracts in English

JAEA Reports

None

Yamasaki, Shinichi*

JNC TJ8430 2000-005, 159 Pages, 2000/03

JNC-TJ8430-2000-005.pdf:3.95MB

no abstracts in English

JAEA Reports

None

PNC TJ1601 98-004, 16 Pages, 1998/03

PNC-TJ1601-98-004.pdf:3.05MB

no abstracts in English

JAEA Reports

None

PNC TN1410 97-041, 29 Pages, 1997/11

PNC-TN1410-97-041.pdf:1.35MB

no abstracts in English

JAEA Reports

None

; Koakutsu, Masayuki; *; Yoshida, Michihiro; ; *;

PNC TN8450 91-006, 77 Pages, 1991/03

PNC-TN8450-91-006.pdf:2.09MB

None

JAEA Reports

None

; Koakutsu, Masayuki; *; Yoshida, Michihiro; ; *;

PNC TN8450 91-005, 103 Pages, 1991/02

PNC-TN8450-91-005.pdf:2.7MB

None

JAEA Reports

Study on radiation-induced deterioration of grease at high temperature, I; Test method on thermal aging

*; Arakawa, Kazuo; Sasuga, Tsuneo; *; *; *; *; Hagiwara, Miyuki; Seguchi, Tadao

JAERI-M 90-010, 24 Pages, 1990/02

JAERI-M-90-010.pdf:0.89MB

no abstracts in English

JAEA Reports

Study on Plasma Shutdown of JAERI Experimental Fusion Reactor

*; Tone, Tatsuzo; *

JAERI-M 7635, 31 Pages, 1978/04

JAERI-M-7635.pdf:0.9MB

no abstracts in English

Oral presentation

Observation of Barnett effect in a paramagnetic state

Ono, Masao; Harii, Kazuya; Okayasu, Satoru; Chudo, Hiroyuki; Matsuo, Mamoru; Ieda, Junichi; Maekawa, Sadamichi; Saito, Eiji*

no journal, , 

no abstracts in English

Oral presentation

Preparation and characterization of simulated fuel debris specific to the Fukushima accident

Takano, Masahide; Nishi, Tsuyoshi; Onozawa, Atsushi

no journal, , 

Since the severe accident at the Fukushima Daiichi Nuclear Power Plant, we have been studying the characteristics of fuel debris in order to contribute to its removal operation and management. First, a series of reaction experiment on (U,Zr)O$$_{2}$$ with natural sea salt were performed to clarify the chemical influence of sea salt deposit on high-temperature corium. It was found that CaO decomposed from sulphate is most reactive to form (U,Zr,Ca)O$$_{2}$$ solid solution or Ca-U-O uranate on the surface, depending on the oxygen partial pressure. Then, some compacted mixtures of B$$_{4}$$C, stainless steel, Zr, and (U,Zr)O$$_{2}$$ were arc-melted to investigate the boron-containing compounds in the fuel debris. ZrB$$_{2}$$ and (Fe,Cr,Ni)$$_{2}$$B were found to precipitate in the alloy part of solidified sample. The phase relationships within these borides and alloy phases can be characterized by the initial B/Zr ratio in the mixture.

Oral presentation

Observation of Barnett effect in paramagnetic state gadolinium

Ono, Masao; Harii, Kazuya; Okayasu, Satoru; Chudo, Hiroyuki; Matsuo, Mamoru; Ieda, Junichi; Maekawa, Sadamichi; Saito, Eiji

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Evaluation of FP chemistry under sever accident conditions with focuses on the effects of BWR control material, 4; Development of experimental technique for analysis FP aerosol using cascade impactor

Takai, Toshihide; Sato, Isamu; Yamashita, Shinichiro; Furukawa, Tomohiro; Osaka, Masahiko

no journal, , 

Property evaluation methods of aerosol, which was released from the simulated FP release test apparatus, were considered, as part of the direct measurement technique of FP's chemical form. It is important to prevent thermal flow from having an effect by installing instruments, for evaluating aerosol property (chemical form, particle diameter distribution, and shape) under simulated severe accident conditions correctly. A low flow cascade impactor with a gas flow control system was installed to the test apparatus, and applicability for aerosol property evaluation was confirmed by heating test using simulated CsI.

Oral presentation

Characterization of fuel debris (28'A), 3; Influence of minor additives on the phase relationships of (U,Zr)O $$_{2}$$ simulated fuel debris

Takano, Masahide; Onozawa, Atsushi; Sudo, Ayako

no journal, , 

no abstracts in English

26 (Records 1-20 displayed on this page)