Restoration of the corrosion department of the reprocessing facilities analysis waste fluid plumbing

Nishida, Naoki; Suwa, Toshio; Tanaka, Naoki; Inada, Satoshi; Kuno, Takehiko

Nihon Hozen Gakkai Dai-11-Kai Gakujutsu Koenkai Yoshishu, p.121 - 126, 2014/07

Corroded pore was found at stainless pipe for liquid waste solution from the analytical laboratory. Part of the pipe was cut for preparing samples to investigate the cause of the corrosion. The same size of stainless pipe was welded to recover it, under the strict radiation control. The restoration work was done inside of the vinyl house, as it is called "greenhouse", which was the small room completely separated by vinyl sheet. All the works, cutting, decontamination, digging groove and welding with back seal gas, were done inside of the greenhouse. We report the work method for recovery of corroded pipe containing radioactive materials

Trial-manufacturing and evaluation tests on new material wrapper tube

Fujiwara, Masayuki*; Nishida, Toshio*; *; *

PNC TJ9058 89-003, 67 Pages, 1989/05

PNC-TJ9058-89-003.pdf:3.08MB

The high Cr ferritic/martensitic steels with a superior resistance to swelling are thought to be preferrable for the long-life wrapper tube materials of the large-scale FBR's. To evaluate the applicability of the ferritic/martensitic steels strengthened by solid-solution and carbide precipitation for the wrapper tubes, the material design to fullfil the requirements for the tensile and the impact properties, and the trial-manufacturing test were performed. The composition selected as a basis was 0.14C-0.5Ni-1Cr-0.5Mo-2.0W-0.25V-0.07Nb-0.06N, and the effects of N, V, and Nb contents and the heat-treatment conditions on the tensile and the impact properties were examined. (1)The tensile and yield strength at elevated-temperatures was largely affected by the heat-treatment conditions, while the effect of the chemical compositions on the strength was small. (2)The impact properties were largely affected by both chemical composition and the heat-treatment condition. The higher contents of N, V, and Nb than those of the basic composition increased the DBTT. (3)To fullfil the requirements for the tensile and the impact properties of the wrapper tubes, the basic composition selected in this study and the heat-treatment condition, normalized at 1050C and tempered at 710C, were thought to be suitable. (4)From the manufacturing test of the wrapper tubes applying the selected chemical composition and the heat-treatment condition, the wrapper tubes having high strength and superior impact properties exceed the requirements were obtained.

Study on oxide dispersion strengthened ferritic steels for FBR fuel cladding materials(III A)

Fujiwara, Masayuki*; Nishida, Toshio*; Soshiroda, Tetsuo*; *

PNC TJ9058 88-007, 189 Pages, 1988/08

PNC-TJ9058-88-007.pdf:35.57MB

As the Oxide Dispersion Strengthened (ODS) ferritic steels have excellent resistance to swelling as well as superior strength at elevated temperatures, they are expected for the long life fuel claddings of the large scale FBR's. To evaluate the applicability of the ODS ferritic steels for the fuel claddings, we investigated the effects of the manufacturing conditions, the additional elements (Nb, V, Zr), the combined strengthening of solutin (W,Mo) and dispersion hardenings, and the kinds of the oxide particles (YO, ZrO) on the properties, especially the elevated - temperature strength, of the ODS ferritic steels. (1)The conditions of the mechanical alloying(MA) process using the attritor showed the strong effect on the properties of the ODS steels. The higher energy the alloy powders are given, the better dispersion of the oxide particles is obtained. The higher agitater speed of the attritor is thought to be the most efficient condition among the MA conditions. (2)The mixed oxied were formed in the Nb and Zr added steels, but in the V added steel the formation of the mixed oxides was not observed. The additions of Nb and V raised the elevated - temperature strength, while the addition of Zr showed little effect on the strength. (3)The additions of the solution hardening elements, Mo and W, up to about 2% increased the creep rupture strength. The effect of W was larger than that of Mo. (4)We chose ZrO instead of YO, and studied the effect of ZrO dispersion on the elevated - temperature strength of the ODS ferritic steels. Although the effect of ZrO on the strength is rather smaller than that of YO, the dispersion strengthening by ZrO particles was observed.

Creep test on fuel cladding tube for fast breeder reactor (XVII) A

Fujiwara, Masayuki*; Soshiroda, Tetsuo*; Nishida, Toshio*

PNC TJ9058 88-004, 61 Pages, 1988/03

PNC-TJ9058-88-004.pdf:4.16MB

Elevated-temperature tensile tests and internal creep rupture tests were performed on three kinds of fuel cladding tubes (61FK, 61FSF, 61FS) of high strength ferritic/martensitic steels, domestically test-manufactured in the fiscal year 1986. Diametrical changes during internal creep were also measured on modified type 316 stainless steel tubes test-manufactured for Monju (55MK). The base composition of the high strength ferritic/martensitic tubes was Fe-11%Cr and the additional elements were 0.5%Mo and 2.0%W on the 61FS tubes, 2.2%W on the 6IFSF tubes, and 2.0%Mo on the 61FK tubes, respectively. The structures of the 61FSF and 61FS tube were single phase of tempered martensite, while that of the 61FK tubes with low C content was dual phases of tempered martentsite and -ferrite. The hardness of the 61FK tubes was higher than those of the 61FSF and 61FS tubes. The test results are sumarized as follows: (1)The tensile strength and the 0.2% proof stress of the 61FK tubes were rather higher than those of the 61FSF and 61FS tubes at the test temperature range from R.T. to 800C. The elongation was not different among the tubes. (2)The 61FK tubes showed the highest creep rupture strength among the three kinds of tubes and the strength of the 61FS tubes was rather higher than that of the 61FSF tubes at 600C, while the difference in the strength was not observed at 650C and at a longer period of time. (3)The creep rupture strength at 600 C of the three kinds of tubes was almost equivalent to that of the 59FK tubes test-manufactured in the fiscal year 1984, but the strength was higher than that of the 59FK tubes at 650C. (4)The effect of the interrupted period of time for measuring the diameter on the creep elongation was not found during internal creep of the 55MK tubes at 650C and ...

Deployment of nuclear science simulations and IT infrastructure

Nakajima, Norihiro; Suzuki, Yoshio; Nishida, Akemi; Kushida, Noriyuki; Teshima, Naoya; Takemiya, Hiroshi; Hirayama, Toshio

no journal, , 

With technology to offer the computer resources that a user needed plural computers connected on a network like one computer, the simulation of the field of atomic energy which cooperated with an experiment institution or the database, is developed. Such a technology is so called grid technology, was in use in form such as ITBL and AEGIS. The simulation in the nuclear fusion energy technology and a fast breeder cycle need the larger and a mass of calculation is necessary. In this presentation, some examples are reported such as earthquake proofing calculation, nuclear fusion calculation, and so on.