Zobrazeno 1 - 10
of 18
pro vyhledávání: '"Takeo Asaga"'
Publikováno v:
Nuclear Technology. 189:312-317
A high-resolution X-ray computed tomography (CT) technique was developed that made it possible to obtain fine X-ray CT images of an irradiated fuel assembly. In addition, the density distributions ...
Publikováno v:
IEEE Transactions on Nuclear Science. 59:1397-1400
A nondestructive method making use of X-ray computer tomography (X-ray CT) has been applied to post irradiation examinations (PIEs) of fast breeder reactor (FBR) fuel assemblies. In the X-ray CT system, a 12 MeV X-ray pulse was used in synchronizatio
Publikováno v:
Journal of the Atomic Energy Society of Japan. 53:638-642
Publikováno v:
Journal of Nuclear Materials. 401:86-90
The helium releases were investigated in FBR fuel pins irradiated to high burn-up. The released amounts increased with the increase of burn-up, but no burn-up dependence of their release fraction to total amounts generated was seen. The contents of 2
Autor:
Seichi Sato, Junichi Nemoto, Fedor N. Kryukov, A. A. Mayorshin, Tetsuya Ishii, O. V. Shishalov, Takeo Asaga
Publikováno v:
Journal of Nuclear Science and Technology. 45:263-273
The compression characteristics and effective elastic moduli of granular UO2 compacts were measured to evaluate the mechanical properties of vibro-packed MOX fuels. These properties were incorporated into a pellet-type fuel performance analysis code
Autor:
O. V. Shishalov, V. B. Ivanov, V. A. Kisly, A. A. Mayorshin, F. N. Krukov, Takeo Asaga, K. Maeda, A. G. Ossipenko, V. P. Smirnov, V. G. Dvoretsky, A. E. Novosyolov, V. V. Maltsev, N. N. Oshkanov, A. V. Bychkov, A. F. Gratchyov, Ishii Tetsuya, O. V. Skiba, V. A. Tsykanov, B. A. Vasilyev
Publikováno v:
Journal of Nuclear Science and Technology. 44:504-510
The paper presents results of a demonstration experiment on conversion of 50 kg of weapon-grade plutonium in the form of metal ingots into granulated MOX-fuel to be used for manufacturing fuel pins and 3 fuel assemblies (FAs) for the fast power-gener
Publikováno v:
Journal of Nuclear Materials. 346:244-252
Fission gas release in FBR MOX fuel pins irradiated to high burnup was studied as a function of burnup. Fuel pellets of different microstructures were fabricated by three methods. The pin averaged burnup of fuel pins ranged from 5.8 to 144 MWd/kgM. T
Publikováno v:
Journal of Nuclear Materials. 344:274-280
Distributions of volatile fission products and microstructures were studied at different axial positions in or near the fuel-cladding gap of FBR MOX fuel pins irradiated up to pin average burn-up of 110.6 GWd/t. It was found that most of the volatile
Autor:
Koji Maeda, Takeo Asaga
Publikováno v:
Journal of Nuclear Materials. 327:1-10
In order to study the dependence of the gap width change on the burn-up, the fuel-to-cladding gap widths were investigated by ceramography in a large number of FBR MOX fuel pins irradiated to high burn-up. The dependence of gap widths on the burn-up
Publikováno v:
Journal of Nuclear Materials. 323:108-122
Power-to-melts of uranium–plutonium oxide fuel pins at an initial startup condition were experimentally obtained from the B5D-2 test in the experimental fast reactor JOYO in Oarai Engineering Center. MCNP code calculations were combined with burnup