Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 32

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Development of public dose assessment code for decommissioning of nuclear reactors (DecDose)

Shimada, Taro; Oshima, Soichiro; Ishigami, Tsutomu; Yanagihara, Satoshi

Proceedings of 10th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '05) (CD-ROM), 8 Pages, 2005/09

In order to review an operator's "Decommissioning Plan" applied to the regulatory body for approval accurately and quickly, Public Dose Assessment Code for Decommissioning of Nuclear Reactors (DecDose) was developed. It evaluates public exposure doses for each year during dismantling activities in accordance with the "Decommissioning Plan". DecDose takes account of various exposure pathways such as cloudshine, surface ground deposition, ingestion of seafood, and direct and skyshine radiation based on the quantity of radionuclides discharged to the environment, and containers stored in the facility in consideration of cutting and storage of components and structures. Example evaluations with DecDose have shown that it is a useful tool for assessing public dose during decommissioning of nuclear reactors.

Journal Articles

Derivation methods for clearance levels and safety assessments for very low-level radioactive waste disposal

Okoshi, Minoru

KURRI-KR-56, p.39 - 57, 2001/03

no abstracts in English

JAEA Reports

Annual report on the environmental radiation monitoring around Tokai reprocessing plant FY 1999

; Shinohara, Kunihiko; ; ; ; Takeyasu, Masanori;

JNC-TN8440 2000-007, 141 Pages, 2000/06

JNC-TN8440-2000-007.pdf:3.02MB

Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on "Safety Regulations for the Tokai Reprocessing Plant, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitants due to the radioactivity discharged from the plant during April 1999 to March 2000. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant.

JAEA Reports

None

JNC-TN4420 2000-009, 11 Pages, 2000/06

JNC-TN4420-2000-009.pdf:0.84MB

None

JAEA Reports

Development of an on-site plant analyzer (1); Development of a GUI for building plant models for analyzes and retrieval of real-time plant data

JNC-TN4400 2000-002, 33 Pages, 2000/06

JNC-TN4400-2000-002.pdf:5.22MB

An on-site plant analyzer can provide analysis support in evaluating plant dynamic characteristics when unplanned events occur in a nuclear power station. The plant analyzer contains a plant-dynamics analysis code, which efficiently and quickly analyzes the plant dynamic characteristics. Elements being developed for the on-site plant analyzer include utilities to build plant models for performing analyses and to retrieve plant operation data. The addition of these elements to the analysis code supports the plant-dynamics analysis works in MONJU, in particular, to assist the analyses of start up tests. The system contains the FBR plant-dynamics analysis code "Super-COPD", which is based on the "COPD" code that was used in the safety licensing of MONJU. One feature of the system is that all operations, e.g., assembling plant models for analysis, are prepared using a GUI (Graphical user Interface). In addition to this feature, the system is able to retrieve directly on- and off-line plant data from MIDAS, the Monju Integrated Data Acquisition System. These plant data are used to supply time-dependent boundary conditions for the plant analysis models. For this report, two case studies were performed. First, the analysis result of a turbine trip test at 40% power operation using the full plant model is described. For the second, performance of the IHX model was evaluated using retrieved plant data for boundary conditions. With the development of this system, improvement in the efficiency of analyses of MONJU start-up tests is expected.

JAEA Reports

Use results of MOX fuel in ATR Fugen nuclear power station

Ijima, Takashi; ; Matsumoto, Mitsuo; *

JNC-TN3410 2000-002, 93 Pages, 2000/01

JNC-TN3410-2000-002.pdf:2.54MB

Fugen Nuclear Power Station ("Fugen") is a prototype Advanced Thermal Reactor (ATR), it has been demonstrated the plutonium utilization by loading many Mixed Oxide Fuels (MOX) since the reactor start up March 1979, and no fuel defect had been occurred, The MOX fuel assemblies has the high reliability and has been loaded more than 700 fuel assemblies. This is the largest in the world as a thermal neutron reactor. However, "Fugen" is planning to stop its operation in the year 2003, because the role of the Fugen almost finished. Therefore, we are going to summarize the ATR project including the Plutonium utilization experience. This paper is summarized as part of the experience.

Journal Articles

Derivation methods of clearance levels for nuclear reactors

Okoshi, Minoru; Takahashi, Tomoyuki*; Kimura, Hideo; ; Sakai, Akihiro; Yoshimori, Michiro; Yamamoto, Hideaki

Hoken Butsuri, 34(2), p.187 - 197, 1999/00

no abstracts in English

Journal Articles

Clearance levels for solid materials arising from nuclear reactors in Japan

Nakanishi*; *; Okoshi, Minoru; Takahashi, Tomoyuki*

Proceedings of 2nd International Symposium on Release of Radioactive Material from Regulatory Control, p.55 - 63, 1999/00

no abstracts in English

JAEA Reports

Safety research in nuclear fuel cycle at PNC

PNC-TN1410 98-018, 69 Pages, 1998/09

PNC-TN1410-98-018.pdf:2.0MB

This report collects the results of safety research in nuclear fuel cycle at power reactor ans nuclear fuel development corporation, in order to answer to the questionnaire of OECD/NEA. The questionnaire request to inelude information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: (1) Recently completed reseach projects (2) Ongoing (current) research projects achievements on following items are omitted by request of oecd/nea. Uranium mining and milling, uranium refining and conversion to UF$$_{6}$$, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning we select topics from the fields of a (1) Nuclear installation, (2) Seismic, and (3) PSA, in projects from frame of annual safety research plan for nuclear installations established by nuclear safety ...

Journal Articles

A Study on aerosol particle behaviors in dismantling nuclear facilities

; Tachibana, Mitsuo; Yanagihara, Satoshi

Proc. of SPECTRUM'98, p.227 - 232, 1998/00

no abstracts in English

JAEA Reports

ATR Data base 「Fugen」 design/ R&D /characteristics [Thermal/Hydraulic]

PNC-TJ1409 97-021, 27 Pages, 1997/03

PNC-TJ1409-97-021.pdf:0.59MB

1 Reflection of R&D Results, Design and Operation Experiences All knowledge obtain in the project, such as R&D results, design, operation experiences and so on, are tbe reflected to following items. 1) Improvement of safety and reliability in plant eration 2) Design modification of the plant 3) Design of the next plant 2 Basic Sndpoint for Data Base Composition "Design/R&D/Plant Performance Data Base" will be mposed ad shown in the following, so that the Data Base could be utilized for reflecng them to the above items and for improving the above items, effectively and efficitly. (1) United Data Bases of Design and R&D "Design/R&D/Plant Performance Data Ba" will be composed by uniting design data base and R&D data base, considering that t R&D of the project is mainly made in order to establish the design engineering and chnical basis, such as design policy, design criteria, design conditions, alloable dign limits, design verification, etc. (2) Addition of Initial Plant Performa

JAEA Reports

ATR Date Bese 「Fugen」 Design/R&D/Characteristics[Nuclear]

PNC-TJ1409 97-020, 29 Pages, 1997/03

PNC-TJ1409-97-020.pdf:0.67MB

1 Reflection of R&D Results, Design and Operation Experiences All knowledge obtain in the project, such as R&D results, design, operation experiences and so on, are tbe reflected to following items. 1) Improvement of safety and reliability in plant eration 2) Design modification of the plant 3) Design of the next plant 2 Basic Sndpoint for Data Base Composition "Design/R&D/Plant Performance Data Base" will be mposed ad shown in the following, so that the Data Base could be utilized for reflecng them to the above items and for improving the above items, effectively and efficitly. (1) United Data Bases of Design and R&D "Design/R&D/Plant Performance Data Ba" will be composed by uniting design data base and R&D data base, considering that t R&D of the project is mainly made in order to establish the design engineering and chnical basis, such as design policy, design criteria, design conditions, alloabledesignlimits, design verification, etc. (2) Addition of Initial Plant Performa

JAEA Reports

Seismic design of reactors in NUCEF

*; *; *; *; ; Sakuraba, Koichi; Izawa, Naoki; Takeshita, Isao

JAERI-Tech 97-010, 276 Pages, 1997/03

JAERI-Tech-97-010.pdf:8.45MB

no abstracts in English

Journal Articles

Development of reactor decommissioning technologies; Completion of the JPDR decommissioning program

Tanaka, Mitsugu

Nippon Kikai Gakkai-Shi, 100(938), 93 Pages, 1997/01

no abstracts in English

JAEA Reports

None

*; *

PNC-TJ1600 96-005, 52 Pages, 1996/03

PNC-TJ1600-96-005.pdf:1.4MB

no abstracts in English

Journal Articles

Decommissioning of nuclear ship Mutsu

Fujikawa, Seigo; Kitamura, Toshikatsu; *; *; *; *

Techno Marine, 0(797), p.853 - 857, 1995/11

no abstracts in English

JAEA Reports

None

; ; Kano, Yutaka; ;

PNC-TN8520 94-008, 37 Pages, 1994/09

PNC-TN8520-94-008.pdf:1.91MB

None

32 (Records 1-20 displayed on this page)