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JAEA Reports

Long-term durability test of acid recovery evaporators made of Ti-5% Ta aIloy and zirconium

; *; *; ; Koyama, Tomozo

JNC-TN8410 2001-013, 255 Pages, 2001/05

JNC-TN8410-2001-013.pdf:24.24MB

Mock-ups of acid recovery evaporators which are made of Ti-5% Ta alloy and Zr were tested under inactive condition for forty thousands hours to improve a corrosion resistance of acid recovery evaporator in Tokai reprocessing plant (TRP). The mock-up unit was designed and produced referring to the specification of acid recovery evaporator in TRP and the evaporation performance of the mock-up was 1/27 of TRP. A long-term durability of both evaporators was demonstrated by results of operation data, evaporation performance and corrosion resistance. The mock-up unit did not suffer from any trouble during the running test and the operation data such as temperature, flow, concentrations of nitric acid and metal ions were fairly stable within standard condition. As for the corrosion resistance, cracks and local corrosion such as intergranular attack were not observed on both evaporators after the running test, and a corrosion of weld was not selective. The average corrosion rates at measuring points were less than 0.1mm/yr, respectively, however, thickness of the Ti-5% Ta alloy evaporator was slightly reduced at all points of vapor phase region. In addition, from the result by test coupon, it is found that both materials have low susceptibility to stress corrosion cracking in this environment. The destructive inspection showed that the mechanical properties of both materials were not degraded during the running test. Finally, the total running time of the mock-up unit is much more than a maximum running time of acid recovery evaporator made of stainless steel in TRP (nearly 15,000 hours). On the basis of the test results, an excellent durability of Ti-5% Ta alloy and Zr evaporators under was successfully demonstrated throughout the mock-up test from an engineering perspective.

JAEA Reports

Design concepts for overpack

*; *; Tanai, Kenji

JNC-TN8400 99-047, 54 Pages, 1999/11

JNC-TN8400-99-047.pdf:3.16MB

This paper reports on the design process for a carbon-steel overpack as a key component in the engineered barrier system of a deep geological repository described in the 2nd progress report. The results of the research and development regarding design requirements, configuration, manufacturing and inspection of overpack are also described. The concept of a composite overpack composed of two different materials is also considered. First, the design requirements for an overpack and presume environmental and design conditions for a repository are provided. For a candidate material of carbon steel overpack, forging material is selected considering enough experience of using this material in nuclear power boilers and other components. Second, loading conditions after emplacement in a repository are set and the pressure-resistant thickness of overpack is calculated. The corrosion thickness to achieve an assigned 1000 year life time and the required thickness to prevent radiolysis of ground water which might enhance corrosion rate are also determined. As aresult, the total required thickness of a carbon-steel overpack is conservatively estimated to 190 mm. This is a reduction of about 30% from the previous estimate provided in the 1st Progress Report. Additional items that must be considered in manufacturring and operating overpacks (i.e. sealing of vitrified waste, examination of main body and sealing welding, mechanism of handling) are evaluated on the basis of current technology, specific future data needs are identified. With respect to the concept of composite overpack (i.e., an outer vessel to provide corrosion-allowance or corrosion-resistant performance and an inner vessel to provide pressure-resistance), the differences in design concepts between the carbon-steel overpack and such composite overpacks are analyzed. Future data needs and analytical capabilities with respect to overpacks are also summarized.

JAEA Reports

ITER breeding blanket module design & analysis

Kuroda, Toshimasa*; Enoeda, Mikio; *; *; Sato, Shinichi*; Osaki, Toshio*; Furuya, Kazuyuki; Hatano, Toshihisa; Sato, Satoshi; Takatsu, Hideyuki

JAERI-Tech 98-051, 71 Pages, 1998/11

JAERI-Tech-98-051.pdf:2.74MB

no abstracts in English

JAEA Reports

Design of intermediate heat exchanger for the HTGR-closed cycle gas turbine power generation system

; Hada, Kazuhiko; Koikegami, Hajime*; Kisamori, Hiroyuki*

JAERI-Tech 96-042, 41 Pages, 1996/10

JAERI-Tech-96-042.pdf:1.35MB

no abstracts in English

JAEA Reports

Development and trial manufacturing of 1/2-scale partial mock-up of blanket box structure for fusion experimental reactor

Hashimoto, T.*; Takatsu, Hideyuki; Sato, Satoshi; Kurasawa, Toshimasa; Mori, Seiji*; Tada, Eisuke; Kuroda, Toshimasa*; Mori, Kensuke*; *; Seki, Masahiro

JAERI-Tech 94-009, 70 Pages, 1994/07

JAERI-Tech-94-009.pdf:5.11MB

no abstracts in English

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