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JAEA Reports

Prototype fast breeder reactor Monju; Its history and achievements

Tsuruga Comprehensive Research and Development Center

JAEA-Technology 2019-007, 159 Pages, 2019/07

JAEA-Technology-2019-007.pdf:19.09MB
JAEA-Technology-2019-007-high-resolution1.pdf:42.36MB
JAEA-Technology-2019-007-high-resolution2.pdf:33.56MB
JAEA-Technology-2019-007-high-resolution3.pdf:38.14MB
JAEA-Technology-2019-007-high-resolution4.pdf:48.82MB
JAEA-Technology-2019-007-high-resolution5.pdf:37.61MB

This report summarizes the history and achievements of the prototype fast breeder reactor Monju. The development of Monju started in 1968 as a prototype reactor following the experimental fast reactor Joyo. The development covers all the activity related to the fast reactor; plant design, mockup tests, construction, operation, and plant management. This report summarizes the history and achievements for 11 technical areas: history and principal achievements, design and construction, operation test, plant safety, core physics, fuel, plant system, sodium technology, materials and mechanical design, plant management, and trouble management.

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.

Journal Articles

Groundwater flow modeling in construction phase of the Mizunami Underground Research Laboratory project

Onoe, Hironori; Saegusa, Hiromitsu; Takeuchi, Ryuji

Doboku Gakkai Rombunshu, C (Chiken Kogaku) (Internet), 72(1), p.13 - 26, 2016/01

AA2015-0210.pdf:4.75MB

The Japan Atomic Energy Agency is conducting the Mizunami Underground Research Laboratory (URL) project in Mizunami, Gifu, in order to establish scientific and technical basis for geological disposal of high-level radioactive waste. This paper comprehensively describes the result of groundwater flow modeling using data of hydraulic responses and hydrochemical changes due to URL construction. Technical know-how and methodology of hydrogeological monitoring and groundwater flow modeling were presented for characterization of hydraulic heterogeneities in fractured crystalline rock. Furthermore, effectivity of data acquisition of hydrochemical changes in groundwater for validation of result of groundwater flow modeling was indicated.

Journal Articles

Design features and cost reduction potential of JSFR

Kato, Atsushi; Hayafune, Hiroki; Kotake, Shoji*

Nuclear Engineering and Design, 280, p.586 - 597, 2014/12

 Times Cited Count:3 Percentile:64.45(Nuclear Science & Technology)

To improve the economic competitiveness of the Japan Sodium-cooled Fast Reactor (JSFR), several innovative designs have been introduced, e.g. reduction of number of main cooling loop, shorter pipe arrangement by adopting thermally durable material, a compact reactor vessel (RV), integration of a primary pump and an intermediate heat exchanger (IHX). A new approach for construction cost estimation has been introduced to handle innovative technologies, for example, concerning different kinds of material, fabrication processes of equipment etc. As results of cost estimations and the latest conceptual JSFR design, economic goals of Generation IV nuclear energy systems can be achieved by expecting the following cost reduction effects: commodity reduction by adopting innovative design, economy of scale by power generation increase, learning effect etc.

Journal Articles

Toward construction of ITER

Shimomura, Yasuo

Purazuma, Kaku Yugo Gakkai-Shi, 81(3), p.143 - 148, 2005/03

The objective of ITER Project is to investigate burning plasmas, to sustain a fusion power of 500 MW for a long period and to demonstrate technologies essential for a power reactor. A steady progress is being made in the technical preparation toward the start of construction on the basis of developments attained during the Engineering Design Activity (EDA), which was completed in 2001. The ITER Negotiators have developed a draft Joint Implementation Agreement (JIA), ready for completion following the nomination of the Director General of the Project(DG). The final high-level negotiations are focused on siting and the concluding details of cost sharing. The EU, with Cadarache, and Japan, with Rokkasho, have both promised large contributions to the project to strongly support their construction site proposals. Large contributions to a broader collaboration among the Parties are also proposed by them. This covers complementary activities to help accelerate fusion development towards a viable power source, and may allow the Participants to reach a conclusion on ITER siting.

Journal Articles

J-PARC commissioning results

Hasegawa, Kazuo

Proceedings of 2005 Particle Accelerator Conference (PAC '05) (CD-ROM), p.220 - 224, 2005/00

no abstracts in English

Journal Articles

Review of the J-PARC project

Hasegawa, Kazuo

Proceedings of 34th ICFA Advanced Beam Dynamics Workshop on High Power Superconducting Ion, Proton and Multi-Species Linacs (HPSL 2005) (Internet), 7 Pages, 2005/00

no abstracts in English

Journal Articles

Status of the J-PARC linac

Hasegawa, Kazuo; High-intensity Proton Accelerator Linac Group

Proceedings of 28th Linear Accelerator Meeting in Japan, p.66 - 68, 2003/08

no abstracts in English

Journal Articles

A Project of the K900 JAERI superconducting AVF cyclotron at JAERI

Fukuda, Mitsuhiro; Okumura, Susumu; Ishii, Yasuyuki; Saito, Yuichi; Miyawaki, Nobumasa; Mizuhashi, Kiyoshi; Agematsu, Takashi; Kurashima, Satoshi; Chiba, Atsuya; Sakai, Takuro; et al.

Dai-14-Kai Kasokuki Kagaku Kenkyu Happyokai Hokokushu, p.302 - 304, 2003/00

no abstracts in English

Journal Articles

High temperature gas-cooled reactor

Muto, Yasushi; Kunitomi, Kazuhiko

Karyoku Genshiryoku Hatsuden, 52(10), p.1279 - 1286, 2001/10

no abstracts in English

JAEA Reports

An Analysis on the economics of plutonium recycle

Tatematsu, Kenji; Tanaka, Yoji*; Sato, Osamu

JAERI-Research 2001-014, 25 Pages, 2001/03

JAERI-Research-2001-014.pdf:2.23MB

no abstracts in English

Journal Articles

A Design study of advanced hydrogen isotope separation system for ITER

Iwai, Yasunori; Yamanishi, Toshihiko; Nishi, Masataka

Fusion Technology, 39(2-Part2), p.1078 - 1082, 2001/03

no abstracts in English

JAEA Reports

Measures of closing report of outside waste storage pits; Separate Volume Part I; Photographs sbout improvement step of outside waste storage pits

; *; Sukegawa, Yasuhiro*; Miyo, Hiroaki

JNC-TN8440 2000-021, 180 Pages, 2000/10

JNC-TN8440-2000-021.pdf:42.37MB

At outside waste storage pits, containers for storage of wastes corroded and were flooded, and it was confirmed on August 26, 1997. Confirmation of contamination of the pits outskirts, installation of sheets to prevent rainwater from flowing into the pits, drawing stay water were executed, promptly. Design and authorization works of the work house and waste treatment devices to take out wastes of the pits were executed too. After construction of the work house, taking out wastes of the pits started, and finished on April 10, 1998. Investigations of the inflow point of rainwater and leak of stay water were executed next. The results were reported to Science and Thechnology Agency (STA), adjoining authorities on December 21, 1998. After decontamination of the pits inner walls to background level of the radioactivity which included general concrete, control area was removed, and the pits were closed by concrete. Measures of closing of the pits were prepared from the middle of August, 1999, and dismantlement of unnecessaly instruments started. Decontamination of the pits started fiom the beginning of September, 1999. The above works finished on June 30, 2000. After decontamination of the pits, STA, adjoining authorities confirmed the circumstances. Work pouring concrete into the pits was executed three times (three levels), and finished on August 31, 2000. In addition to above, the amount of concrete poured into the pits was about 1,200 m$$^{3}$$. This report compiled the photographs of the works from confirmation of stay water at August, 1997 by finish of measures of closing of the pits at September, 2000.

JAEA Reports

Integrated disposal system concering to waste of RI and research institute

Hagiwara, Shigeru*; Sakamoto, Yoshiaki; Takebe, Shinichi; Okuda, Katsuzo*; Ogawa, Hiromichi

JAERI-Research 2000-039, 119 Pages, 2000/09

JAERI-Research-2000-039.pdf:5.04MB

no abstracts in English

JAEA Reports

None

*

JNC-TJ6420 2000-005, 109 Pages, 2000/07

JNC-TJ6420-2000-005.pdf:3.16MB

no abstracts in English

JAEA Reports

Studies on sodium cooled fast breeder reactor

Nibe, Nobuaki; Shimakawa, Yoshio; ; ; ; ;

JNC-TN9400 2000-074, 388 Pages, 2000/06

JNC-TN9400-2000-074.pdf:13.32MB

Large sized sodium-cooled fast breeder reactors of large-size are being studied and have been operated in Japan and many countries. ln this feasibility study, evaluation was made on technical feasibinty for design concepts or 1 loop type and 3 pool types, specially from the viewpoint of improvement of economical competence. The design concepts include the ideas of cost reduction measures such as large-scaled components, reduction of loop number and integration of components on the basic of utilization of sodium characteristics. From the results of the evaluation, it may be possible for all the concepts to attain the economical target of 200 thousands yen per kilowatt, though further confirmation should be made for technical feasibility of those concepts. ln addition, the following items were listed up as further cost-reduction measures. (1)Higher temperature cooling system and steam cycle efficiency (2)Shortening of construction term (3)Reduction of safety systems by using measuring instruments with high performmce (4)Adoption of SG-ACS

JAEA Reports

lnvestigation of small and modular-sized fast reactor

; Kawasaki, Nobuchika; ; *; ; ;

JNC-TN9400 2000-063, 221 Pages, 2000/06

JNC-TN9400-2000-063.pdf:8.68MB

ln this paper, feasibility of the multipurpose small fast reactor, which could be used for requirements concemed with various utilization of electricity and energy and flexibility of power supply site, is discussed on the basis of examination of literatures of various small reactors. And also, a possibility of economic improvement by learning effect of fabrication cost is discussed for the modular-sized reactor which is expected to be a base load power supply system with lower initial investment. (1)Multipurpose small reactor (a)The small reactor with 10MWe$$sim$$150MWe has a potential as a power source for large co-generation, a large island, a middle city, desalination and marine use. (b)Highly passive mechanism, long fuel exchange interval, and minimized maintenance activities are required for the multipurpose small reactor design. The reactor has a high potential for the long fuel exchange interval, since it is relatively easy for FR to obtain a long life core. (c)Current designs of smalI FRs in Japan and USA (NERI Project) are reviewed to obtain design requitements for the multipurpose small reactor. (2)Modular-sized reactor (a)ln order that modular-sized reactor could be competitive to 3200MWe twin plant (two large monolithic reactor) with 200k/kWe, the target capital cost of FOAK is estimated to be 260k/kWe for 800MWe modular, 280k/kWe for 400MWe modular and 290k/kWe for 200MWe by taking account of the learning effect. (b)As the result of the review on the current designs of modular-sized FRs in Japan and USA (S-PRISM) from the viewpoint of economic improvement, since it only be necessaly to make further effort for the target capital cost of FOAK, since the modular-sized FRs requires a large amount of material for shielding, vessels and heat exchangers essentially.

JAEA Reports

TCMD Intranet system integration (Part 2)

Kon, Tetsuro

JNC-TN8440 2000-004, 93 Pages, 2000/03

JNC-TN8440-2000-004.pdf:3.7MB

TCMD (Tokai Construction Maintenance Division) Intranet System Integration has started in 1995. The first active activities between 1995 and 1996 has reported in a previous PNC report (PNC PN8440 97-032 TCMD Intranet System Integration Part 1). This is the second active activity's report between 1997 and 1999. Main content of this report is as follows. TCMD Intranet System Integration has completed by TCMD LAN system construction with high-speed LAN equipments and WINS services. TCMD group scheduler and conference rooms appointment system has developed by the operation of Exchange Server 5.5. The plant construction management data base system has developed ---ACCESS 97/SQL Server 6.5 version. The plant construction management data base system has also developed---Internet Explorer / Active Server Pages version. The formal TCMD homepage service has begun in l998.

JAEA Reports

An Investigation of cementitious materials for radioactive waste repository; Mechanical properties of law alkalinity cementitious materials

Owada, Hitoshi*; ; Iriya, Keishiro*; *

JNC-TN8400 99-057, 43 Pages, 2000/03

JNC-TN8400-99-057.pdf:2.45MB

Cementitious materials are considered as candidate materials for the geological disposal of high-level radioactive waste and TRU waste. As the pH and the Ca content of leachate from the cementitious materials are high, the host rock and the buffer-material would be degraded by the leachate in the long-term. Therefore, transport properties and parameters such as solubilities and distribution coefficients of radionuclides would be changed and affect the performance of the repository. In order to dissolve this "High pH plobrem", the use of a low alkalinity cement is considered for the disposal. In this study, we summarized the necessity of the low alkalinity cement, and developed the approach of the low alkalinization of cement. And, the following were carried out in this study : A leaching test of cement paste, a fluid test of the mortar and a installation test of the concrete to the trial structure. From the leaching test using the cement paste, we confirmed that we were able to obtain the low alkalinity cement (HFSC) by addition of pozzolanic materials such as silica-fume and flyash. From the result of the fluid test of the mortar, we chose the cement for the practicability evaluation. The practicability of low alkalinity concrete was evaluated by installation test to the trial structure.As a result of these examinations, we proved that the pH value of the leachate from the cementitious material was reduced by adding SF and FA to Portland cement. Simultaneously, SF and FA had to be added in order to obtain the good workability. In addition, workability and mechanical strength of the cement which SF and FA were added are almost equivalent to the ordinary Portland cement. The results shows that the HFSC has high practicability.

JAEA Reports

None

JNC-TN4420 2000-004, 9 Pages, 2000/03

JNC-TN4420-2000-004.pdf:3.04MB

no abstracts in English

80 (Records 1-20 displayed on this page)