ITER nuclear components, preparing for the construction and R&D results

Ioki, Kimihiro*; Akiba, Masato; Barabaschi, P.*; Barabash, V.*; Chiocchio, S.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Ezato, Koichiro; Federici, G.*; et al.

Journal of Nuclear Materials, 329-333(1), p.31 - 38, 2004/08

https://doi.org/10.1016/j.jnucmat.2004.04.003

The preparation of the procurement specifications is being progressed for key components. Progress has been made in the preparation of the procurement specifications for key nuclear components of ITER. Detailed design of the vacuum vessel (VV) and in-vessel components is being performed to consider fabrication methods and non-destructive tests (NDT). R&D activities are being carried out on vacuum vessel UT inspection with waves launched at an angle of 20 or 30 degree, on flow distribution tests of a two-channel model, on fabrication and testing of FW mockups and panels, on the blanket flexible support as a complete system including the housing, on the blanket co-axial pipe connection with guard vacuum for leak detection, and on divertor vertical target prototypes. The results give confidence in the validity of the design and identify possibilities of attractive alternate fabrication methods.

Nuclear, thermo-mechanical and tritium release analysis of ITER breeding blanket

Kosaku, Yasuo; Kuroda, Toshimasa*; Enoeda, Mikio; Hatano, Toshihisa; Sato, Satoshi; Sato, Shinichi*; Osaki, Toshio*; Miki, Nobuharu*; Akiba, Masato

JAERI-Tech 2003-058, 69 Pages, 2003/06

JAERI-Tech-2003-058.pdf:5.86MB

The design of the breeding blanket in ITER applies pebble bed breeder in tube (BIT) surrounded by multiplier pebble bed. It is assumed to use the same module support mechanism and coolant manifolds and coolant system as the shielding blankets. This work focuses on the verification of the design of the breeding blanket, from the viewpoints which is especially unique to the pebble bed type breeding blanket, such as, tritium breeding performance, tritium inventory and release behavior and thermo-mechanical performance of the ITER breeding blanket.

Criticality safety evaluation of multiple units in Tokai Reprocessing Plant

Shirai, Nobutoshi; Taguchi, Katsuya; Iitsuka, Shoji; ; *; Sudo, Toshiyuki

JNC TN8410 99-055, 69 Pages, 1999/09

JNC-TN8410-99-055.pdf:2.98MB

As a part of the safety confirmation work of Tokai Reprocessing Plant, an assessment of the basic data for criticality safety and shielding design has already been reported. In that report, two plutonium solution storage cells were evaluated to be safe enough from a viewpoint of multiple unit criticality safety. In this report, additionai evaluation of multiple unit criticality safety was made for the main plant and the UO storage which were designed in 1960's and constructed in 1970's. The evaluated cells and rooms are enriched uranium dissolution cell, adjustment and feeding cell, two second extraction cycle cells, third uranium cycle cell, uranium concentration and denitration rooms, third plutonium cycle cell, plutonium concentration cell, two plutonium solution storage cells, rework cell, and UO storage room. As a result, it was confirmed that these cells and rooms were safe enough from a viewpoint of multiple unit criticality safety.

Japanese Contributions to IAEA INTOR Workshop,PhaseIIA,Part 2, Chapter III:Impurity Control(Engineering)

Seki, Masahiro; *; *; ; *; *; *; *; *

JAERI-M 85-075, 177 Pages, 1985/07

JAERI-M-85-075.pdf:3.35MB

no abstracts in English