Desgin study of advanced nuclear fuel recycle system; Conceptual study of recycle system using molten salt

Kakehi, Isao; ; ; ; ; Kajitani, Yukio;

PNC TN9410 97-015, 382 Pages, 1996/12

PNC-TN9410-97-015.pdf:12.32MB

For the purpose of developing the future nuclear fuel recycle system, the design study of the advanced nuclear fuel recycle system is being conducted. This report describes intermediate accomplishments in the conceptual system study of the advanced nuclear fuel recycle system. Fundamental concepts of this system is the recycle system using molten salt which intend to break through the conventional concepts of purex and pellet fuel system. Contents of studies in this period are as follows, (1)feasibility study of the process by Cd-cathode for nitride fuel (2)application study for the molten salt of low melting point (AlCl+organic salt)(3)research for decladding (advantage of decladding by heat treatment)(4)behavior of FPs in electrorefinning (behavior of iodine and volatile FP chlorides, FPs behavior in chlorination) (5)criticaliy analysis in electrorefiner (6)drawing of off-gas flow diagram (7)drawing of process machinery concept (cathode processor, vibration packing) (8)evaluation for the amounts of the high level radioactive wastes (9)quality of the recycle fuels (FPs contamination of recycle fuel) (10)conceptual study of in-cell handling system (11)meaning of the advanced nuclear fuelrecycle system. The conceptual system study will be completed in describing concepts of the system and discussing issues for the developments.

Report of the 2nd through 7th Conferences of Special Committee on Nuclear Criticality Safety

JAERI-Review 95-001, 188 Pages, 1995/02

JAERI-Review-95-001.pdf:5.04MB

no abstracts in English

Reports of results of mock-up test concerning the remote piping work system

Tanaka, Yoji*; Nakasawa, Otohiko*; Sugumoto, Hiroshi*; Takeshita, Hiroshi*

PNC TJ8224 92-002, 33 Pages, 1992/03

PNC-TJ8224-92-002.pdf:1.06MB

no abstracts in English

Critical Experiments Facility and Criticality Safety Programs at JAERI

; ; ; ; Miyoshi, Yoshinori;

JAERI-M 85-152, 17 Pages, 1985/10

JAERI-M-85-152.pdf:0.56MB

no abstracts in English

Current R&D status of HTGR and hydrogen production process in JAEA

Kubo, Shinji

no journal, , 

no abstracts in English