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Yamanaka, Shinsuke*; Uno, Masayoshi*; Kurosaki, Ken*; ; Namekawa, Takashi
JNC TY9400 2000-011, 41 Pages, 2000/03
no abstracts in English
Yamanaka, Shinsuke*; Abe, Kazuyuki
JNC TY9400 2000-004, 78 Pages, 2000/03
no abstracts in English
*;
JNC TN9400 2000-047, 114 Pages, 2000/03
Prediction of weld residual stresses by a general finite element code is beneficial to the improvement of the accuracy of integrity assessment and residual life assessment of FBR plants. This reports develops an evaluation method of weld residual stresses using FINAS. Firstly, we suggested a basic procedure derived from parametric analyses with a simple weld joint model. The procedure can be summarized as follows: (1)For heat conduction analysis, prepare different models corresponding to the number of layers to be modeled. Hand over the analytical results to the following model. (2)Use multi-linear stress-strain curves for modeling the stress-strain response of base metal and weld metal. Use the isotropic hardening rule. (3)When metals are melt, use a user-subroutine to keep stresses from arising. (4)Put the thermal expansion coefficient as zero when heat is being input. Then, using the above procedure and TIG welding, we predicted the weld residual stresses of plate and tube. The results agreed well with the other reports, showing the suggested procedure was reasonable.
Takachi, Kazuhiko; Suzuki, Hideaki*
JNC TN8400 99-041, 76 Pages, 1999/11
The buffer material is expected to maintain its low water permeability, self-sealing properties, radionuclides adsorption and retardation properties, thermal conductivity, chemical buffering properties, overpack supporting properties, stress buffering properties, etc. over a long period of time. Natural clay is mentioned as a material that can relatively satisfy above. Among the kinds of natural clay, bentonite when compacted is superior because (1)it has exceptionally low water permeability and properties to control the movement of water in buffer, (2)it fills void spaces in the buffer and fractures in the host rock as it swells upon water uptake, (3)it has the ability to exchange cations and to adsorb cationic radioelements. In order to confirm these functions for the purpose of safety assessment, it is necessary to evaluate buffer properties through laboratory tests and engineering-scale tests, and to make assessments based on the ranges in the data obtained. This report describes the procedures, test conditions, results and examinations on the buffer material of unconfined compression tests, one-dimensional consolidation tests, consolidated-undrained triaxial compression tests and consolidated-undrained triaxial creep tests that aim at getting hold of static mechanical properties. We can get hold of the relationship between the dry density and tensile stress etc. by Brazillian tests, between the dry density and unconfined compressive strength etc. by unconfined compression tests, between the consolidation stress and void ratio etc. by one-dimensional consolidation tests, the stress pass of each effective confining pressure etc. by consolidated-undrained triaxial compression tests and the axial strain rate with time of each axial stress etc. by consolidated-undrained triaxial creep tests.
Aoto, Kazumi; ;
PNC TN9410 97-037, 51 Pages, 1996/11
The basic material properties of a rolled steel for welded structure (present standard name is SM400B, old standard name SM41B) which is used as the liner plate in SHTS cells of "Monju plant". Based on the material testing data for evaluation of structural integity of the liner during sodium leakage are tentatively proposed. Main basic material properties are shown as follows. (1)The 0.2% offset yield stress (lower yield point). (2)The ultimate tensile strength. (3)The modulus of the longitudinal elasticity. (4)Static stress-strain relation. (Physical property in Ludwik equation). (5)The creep strain. (6)The linear thermal expansion coefficient. (7)The density. (8)A specific heat. (9)The thermal conductivity.
*; ; Sukegawa, Takenori; Akutsu, Yoichi; *; *
Nihon Kenchiku Gakkai Kozokei Rombunshu, 0(488), p.1 - 10, 1996/10
no abstracts in English
; H.Cords*; H.Nickel*
Journal of Nuclear Science and Technology, 29(9), p.851 - 858, 1992/09
no abstracts in English
; ;
Int. Symp. on Carbon New Prossing and New Applications; Extended Abstracts,Vol. l, p.538 - 541, 1990/11
no abstracts in English
; M.A.Kirk*; R.C.Birtcher*; Hagiwara, Miyuki
Journal of Nuclear Materials, 133-134, p.795 - 799, 1985/00
Times Cited Count:5 Percentile:59.84(Materials Science, Multidisciplinary)no abstracts in English
R.B.McLellan*;
Scr.Metall., 19, p.485 - 488, 1985/00
no abstracts in English
; M.A.Kirk*; R.C.Birtcher*
Journal of Nuclear Materials, 126, p.152 - 159, 1984/00
Times Cited Count:14 Percentile:79.2(Materials Science, Multidisciplinary)no abstracts in English
; *; ; ; Araki, Kunio; ; ; ; *; *; et al.
JAERI-M 83-004, 38 Pages, 1983/02
no abstracts in English
PNC TN241 81-25VOL2, 113 Pages, 1981/11
; ; Ohara, Yoshihiro;
JAERI-M 9539, 22 Pages, 1981/06
no abstracts in English
; ;
JAERI-M 8923, 8 Pages, 1980/07
no abstracts in English
; *;
JAERI-M 6213, 43 Pages, 1975/08
no abstracts in English
;
Nihon Kikai Gakkai-Shi, 69(572), p.1146 - 1154, 1966/00
no abstracts in English