Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Suzuki, Satoru; Sato, Haruo
JNC TN8410 2001-028, 36 Pages, 2002/03
JNC-TN8410-2001-028.pdf:1.81MB
For a safety assessment of the high-level radioactive waste disposal, effective diffusion coefficients (D
) of radionuclides in bentonite have been accumulated by the through-diffusion method. It has been found recently that experimental results on Ds for several cations (cesium and strontium) by the fairly standard experimental method in JNC differ from those previously reported in several papers. Discrepancy can be considered to be due to different design of diffusion cell and system. In order to confirm influences of the experimental design on cation diffusivities in bentonite, a flow-through diffusion system was developed and several diffusion experiments were conducted.As a result, magnitude of D and its salinity dependence were relatively different between the standard and flow-through diffusion system. Since the latter system can control boundary conditions of the experiment more strictly than the standard method, we can conclude that the flow-through diffusion system provide correct results. In addition, we apply this flow-through diffusion system to a modification of controlling boundary condition during the experiment and to the diffusion experiment under controlled temperature.
; ;
JNC TN9400 2000-029, 87 Pages, 1999/11
JNC-TN9400-2000-029.pdf:5.11MB
The second Power-To-Melt (PTM) test, PTM-2, was performed in the experimental fast reactor "JOYO". AIl of the twenty-four fuel pins of the irradiation vehicle, B5D-2, for the PTM-2 test, were provided for post-irradiation-experiment (PIE) to evaluate the PTM values. ln this study, the PIE technique for PTM test was established and the PTM results were evaluated. The findings are as follows: (1) The maximum fuel-melting ratio on the transverse section was 10.7%, and was within the limit of fuel-melting in this PTM test enough. Unexpected fuel-melting amount to a ratio of 11.8% was found at 
24 mm below the peak power elevation in a test fuel pin, lt is possible that this arose from secondary fuel-melting. (2) Combination of metallographical observation with X-ray microanalysis of plutonium distribution was very effective for the identification of once-molten fuel zone. (3) The PTM evaluation suggested that dependence of the PTM on the fuel pellet density was stronger than that of previous foreign PTM tests, while the dependence on the pellet-cladding gap and the oxygen-to-metal ratio was indistinctly. The dependence on the cladding temperature and the fill gas composition was not shown as well.
Seguchi, Tadao
Materiaru Raifu, 9(1), p.20 - 27, 1997/01
no abstracts in English
; ; *; *; *; *; Yoshida, Eiichi
PNC TN9450 91-008, 38 Pages, 1991/09
In order to advancement in materials strength standard on elevated temperature design guide of the FBRs and evaluation method of materials strength behavior, this report are presented about the tensile properties of FBR grade SUS316, based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1)Material : FBR grade SUS316 (Base Metal) B7 Heat 1,000mm
1,000㎜50mm
(Plate) B8 Heat 1,000㎜1,000mm40mm(Plate) B9 Heat 1,000mm1,000㎜25㎜(Plate) (2)Test temperature : RT750
C (3)Test method : According to JIS and FBR Metallic Materials Test Methods (4)Number of deta : 64 points
; ; ; ; ; Yoshida, Kenzo
EIM-83-122, p.65 - 72, 1983/00
no abstracts in English
JAERI-M 7321, 14 Pages, 1977/10
no abstracts in English
Hoshasen, 4(3), p.37 - 43, 1977/03
no abstracts in English
