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.

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

http://doi.org/10.2208/jscejge.72.13

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.

Toward construction of ITER

Shimomura, Yasuo

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

http://ci.nii.ac.jp/naid/110003827841

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.

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

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

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

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

Yoshida, Michihiro; Suzuki, Satoshi*; 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. 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.

None

*

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

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

no abstracts in English

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 10MWe150MWe 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 small FRs in Japan and USA (NERI Project) are reviewed to obtain design requirements 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 necessary 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.

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

Owada, Hitoshi*; Mihara, Morihiro; Iriya, Keishiro*; *

JNC TN8400 99-057, 43 Pages, 2000/03

JNC-TN8400-99-057.pdf:5.13MB

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.