Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 25

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

Impact of safety design enhancements on construction cost of the advanced sodium loop fast reactor in Japan

Kato, Atsushi; Mukaida, Kyoko

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05

Improvement of economic competitiveness is a part of key requirement in the project. By adopting innovative technologies to reduce plant commodities, JSFR could achieve economic competitiveness compared with LWR. After the Fukushima-Dai-ichi Nuclear Power Plants accident, safety enhancement measures were added on LWR in Japan mainly against external hazards. In parallel, Safety Design Criteria and Guidelines (SDC/SDG) for SFR were constructed in the framework of Generation IV international forum. Design studies of JSFR were carried out responding to GIF SDC/SDG and lessons learn from the Fukushima accident. This reports an impact of recent safety design enhancements on JSFR construction cost. Safety design enhancement adopted in JSFR.

JAEA Reports

Safety measures in the melting facilities of The Advanced Volume Reduction Facilities; Document collection of discussion meetings related to melting facilities

Iketani, Shotaro; Yokobori, Tomohiko; Ishikawa, Joji; Yasuhara, Toshiyuki*; Kozawa, Toshiyuki*; Takaizumi, Hirohide*; Monma, Takeshi*; Kurosawa, Shingo*; Iseda, Hirokatsu; Kishimoto, Katsumi; et al.

JAEA-Review 2018-016, 46 Pages, 2018/12

JAEA-Review-2018-016.pdf:12.79MB

Japan Atomic Energy Agency (JAEA) adopts melting process for the waste processing and packaging method of radioactive miscellaneous solid waste in NSRI because melting process is effective in radioactivity evaluation, volume reduction, and stabilization treatment. Metal melting processing facilities, Incinerator, and Nonmetal melting processing facilities (hereinafter referred to as melting process facilities) have taken lots of safety measures, including measures for preventing the recurrence of the fire accidents. To exchange opinions and discuss the validity of these measures and so on with internal personnel and external experts, "Discussions on Melting Process Facilities" was held. As a document collection, this paper summarizes presentation materials of discussion meetings. Presentation materials describe "Outline of AVRF", "Safety measures in the melting facilities in WVRF", "Operation management of the melting facilities in WVRF", "Comparison of the past accident cases between facilities in and outside Japan and WVRF", and "Introduction of past accident cases and safety measures in other facilities from each committee".

Journal Articles

Status of R&D of high-performance monitoring system under sever accident

Tsuchiya, Kunihiko; Takeuchi, Tomoaki; Komanome, Hirohisa*; Miura, Kuniaki*; Araki, Masanori; Ishihara, Masahiro

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.375 - 378, 2016/07

no abstracts in English

Journal Articles

Pressure rise analysis when hydrogen leak from a cracked pipe in the cryogenic hydrogen system in J-PARC

Tatsumoto, Hideki; Aso, Tomokazu; Hasegawa, Shoichi; Ushijima, Isamu*; Kato, Takashi; Otsu, Kiichi*; Ikeda, Yujiro

AIP Conference Proceedings 823, p.753 - 760, 2006/05

As one of the main experimental facilities in J-PARC, an intense spallation neutron source (JSNS) driven by proton beam power of 1 MW is constructed. In JSNS, cryogenic hydrogen at supercritical pressure is selected as a moderator. The total nuclear heating at the moderators is estimated to be 3.7 kW. A cryogenic hydrogen system to cool the moderators has been designed. As the most severe off-normal event for cryogenic hydrogen system, it is considered that the cryogenic hydrogen leaks when the pipe is cracked. In such a case, the hydrogen must be discharged safely as soon as possible. An analytical code that simulated the pressure change during hydrogen leak was developed. The pressure rise analysis for various sized cracks was performed, and then the required size of safety equipment was determined. It was found from the analysis that a safety valve of -42.7 mm and a rupture disk with the diameter of 37.1 mm can discharge hydrogen safely.

JAEA Reports

Safety admimstration division business report; The second quarter of 2001

Kanamori, Masashi

JNC-TN8440 2001-023, 110 Pages, 2001/12

JNC-TN8440-2001-023.pdf:3.91MB

The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these businesses and utilizing the data concerning the businesses, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the second quarter news from July to September in 2001.

JAEA Reports

Safety administration division business report; The first quarter of 2001

Kanamori, Masashi

JNC-TN8440 2001-015, 100 Pages, 2001/09

JNC-TN8440-2001-015.pdf:3.79MB

As a consequence of this reorganization, the business of the Safety Administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, the business of the sanction concerning the Tokai Works, the protection of nuclear materials, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. In the respect of the purpose of summarizing these businesses and utilizing the data concerning the businesses, the report about a business achievement was determined to make.

JAEA Reports

Safety considerations for continuous hydrogen production test apparatus wtih capacity of 50 N-litter hydrogen per hour

Onuki, Kaoru; Akino, Norio; Shimizu, Saburo; Nakajima, Hayato; Higashi, Shunichi; Kubo, Shinji

JAERI-Tech 2001-032, 63 Pages, 2001/03

JAERI-Tech-2001-032.pdf:4.63MB

no abstracts in English

JAEA Reports

None

; *; *

JNC-TN8200 2001-001, 42 Pages, 2001/01

JNC-TN8200-2001-001.pdf:3.16MB

None

JAEA Reports

Conceptual design of the handling and storage system of the spent target vessel for a MW-class neutron scattering facility

Adachi, Junichi*; Kaminaga, Masanori; Sasaki, Shinobu; Hino, Ryutaro

JAERI-Tech 2000-068, 86 Pages, 2000/11

JAERI-Tech-2000-068.pdf:4.39MB

no abstracts in English

JAEA Reports

Disassembly and removal of 50MW steam generator test facility; Disassembly and sodium removal of the large cold trap

JNC-TN9410 2000-003, 52 Pages, 1999/12

JNC-TN9410-2000-003.pdf:3.51MB

In May, 1999, disassembly and cleansing of sodium residues contained in the large cold trap (50MWSG) were carried out. Two cold trap units, one from the primary sodium loop and the other from the for the secondary sodium loop were disassembled and cleaned. This report describes the procedures, methods, and tasks under taken in the clean-up effort, including countermeasures for safe handling of sodium. The disassembly of the cold trap was based an information regarding similar cleansing activities external to JNC. There was also same a priori knowledge of the type and amount of sodium-laden residues. As this result, we conducted disassembly and cleansing task as provisionally planned. In fact we learned that disassembly methods for the specific components could be conducted in an aerated atmosphere. We thus gained additional disassembly and sodium cleansing experience under manageable and safe conditions.

JAEA Reports

Report of radiation exposure control on the 12th periodic inspection at experimental fast reactor JOYO

; Kano, Yutaka; ; Shindo, Katsutoshi

JNC-TN9410 2000-001, 20 Pages, 1999/12

JNC-TN9410-2000-001.pdf:1.84MB

The 12th periodic inspection had been executed at the experimental fast reactor JOYO from February 24,1998 to June 28,1999. This inspection had been extended about three months because it was addtion to the work for the safety countermeasure. The result of collective dose equivalent was 263.92 man*mSv, whereas, the expected collective dose equivalent was about 407 man*mSv in the whole period of this inspection. It was confirmed that this inspection was carried out with the suitable radiation protection programmes. In this report, provided in 12th periodic inspection, were described with taking the results of the past periodic inspections into consideration.

JAEA Reports

Decommissioning of facility for use of radioisotopes on waste management and disposal facility

Takebe, Shinichi; Komiya, Tomokazu

JAERI-Tech 99-068, p.46 - 0, 1999/09

JAERI-Tech-99-068.pdf:2.25MB

no abstracts in English

JAEA Reports

None

JNC-TN1400 99-017, 439 Pages, 1999/08

JNC-TN1400-99-017.pdf:14.06MB

no abstracts in English

JAEA Reports

None

*; *; *; *; *; *; *

PNC-TN1410 94-006, 57 Pages, 1994/11

PNC-TN1410-94-006.pdf:10.29MB

no abstracts in English

JAEA Reports

None

; ;

PNC-TN8440 94-013, 72 Pages, 1994/03

PNC-TN8440-94-013.pdf:2.94MB

None

Journal Articles

Safety practices in radiation facilities

Dai-20-Kai Nihon Aisotopu, Hoshasen Sogo Kaigi Hobunshu, p.207 - 211, 1992/00

no abstracts in English

JAEA Reports

None

; ; ; Nakashima, Yuji; ; ;

PNC-TN9520 92-001, 17 Pages, 1991/10

PNC-TN9520-92-001.pdf:0.53MB

None

JAEA Reports

None

*

PNC-TJ1506 91-001, 217 Pages, 1991/06

PNC-TJ1506-91-001.pdf:8.14MB

None

JAEA Reports

None

Miyoshi, Masahiko*; Fujimura, Masatsune*

PNC-TJ1409 91-001, 278 Pages, 1991/02

PNC-TJ1409-91-001.pdf:9.16MB

None

JAEA Reports

25 (Records 1-20 displayed on this page)