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Journal Articles

Indirect measurement of near-surface velocity and pressure fields based on measurement of moving free surface profiles

Shibamoto, Yasuteru; Kukita, Yutaka*; Nakamura, Hideo

Nihon Kikai Gakkai Rombunshu, B, 71(703), p.825 - 832, 2005/03

no abstracts in English

Journal Articles

BEM-based measurement of pressure field adjacent to moving free surface

Shibamoto, Yasuteru; Kukita, Yutaka*; Nakamura, Hideo

Proceedings of 5th International Conference on Multiphase Flow (ICMF 2004) (CD-ROM), p.217_1 - 217_9, 2004/05

no abstracts in English

JAEA Reports

JAEA Reports

Development of analytical model for evaluating temperature fluctuation in coolant (X); Investigation of thermally response characteristics of in-vessel structures using the BEMSET code

PNC TN9410 96-136, 92 Pages, 1996/05

PNC-TN9410-96-136.pdf:2.53MB

Thermal striping phenomena characterized by stationary random temperature fluctuations are observed in the region immediately above the core exit of liquid-metal-cooled fast breeder reactors (LMFBRs) due to the interactions of cold sodium flowing out of a control rod (C/R) assembly and hot sodium flowing out of adjacent fuel assemblies (F/As). Therefore the in-vessel components located in the core outlet region, such as upper core structure (UCS), flow guide tube, C/R upper guide tube, etc, must be protected against the stationary random thermal process which might induce high-cycle fatigue. In this study, thermally response characteristics of the flow guide tube made by SUS 316 stainless steels were investigated using a boundary element method code BEMSET under the temperature transient conditions of Sine wave, quasi-random wave, and Sine wave with quasi-random components. From the numerical investigations, it was concluded that the detailed handling on turbulence phenomena in coolant is very important in the evaluation of actual LMFBRs, because of the thermally response of the structures are influenced significantly on random fluctuating components.

JAEA Reports

Journal Articles

Three-dimensional isoparametric boundary element method for solving neutron diffusion equations

; *

Journal of Nuclear Science and Technology, 33(1), p.7 - 16, 1996/01

 Times Cited Count:9 Percentile:62.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Boundary element method for criticality safety analyses

ICNC 95: 5th Int. Conf. on Nuclear Criticality Safety, 1, p.6.25 - 6.31, 1995/00

no abstracts in English

Journal Articles

Multiple reciprocity boundary element method for 3-D fission neutron source iterations

; *

Kyokai Yosoho Rombunshu Dai-11-Kan, 0, p.13 - 18, 1994/12

no abstracts in English

Journal Articles

Boundary integral expression of the slowing-down source term in 3-D multi-energy-group neutron diffusion equations

*;

Kyokai Yosoho Rombunshu Dai-11-Kan, 0, p.7 - 12, 1994/12

no abstracts in English

Journal Articles

Geometric buckling expression for regular polygons, II; Analyses based on the multiple reciprocity boundary element method

; Miyoshi, Yoshinori; Hirose, Hideyuki

Nuclear Technology, 103, p.392 - 402, 1993/09

 Times Cited Count:4 Percentile:44.86(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Multiple reciprocity boundary element method applied to neutron diffusion and Helmholtz-type eigenvalue problems

; C.A.Brebbia*

Kyokai Yosoho Kenkyukai BEM, Tekunoroji, Konfarensu Rombunshu, p.59 - 64, 1993/06

no abstracts in English

Journal Articles

Source iterative multiple reciprocity techniques for Helmholtz eigenvalue problems with boundary elements

; C.A.Brebbia*

Boundary Element Methods, p.79 - 88, 1993/00

no abstracts in English

Journal Articles

Multiple reciprocity boundary element formulation for one-group fission neutron source iteration problems

; C.A.Brebbia*

Engineering Analysis with Boundary Elements,11, p.39 - 45, 1993/00

no abstracts in English

Journal Articles

Generation of higher order fundamental solutions to the two-dimensional modified Helmholtz equation

; C.A.Brebbia*

Engineering Analysis with Boundary Elements,11, p.87 - 90, 1993/00

no abstracts in English

Journal Articles

Round-off error accumulation observed in a neutron diffusion calculation using the multiple reciprocity boundary element method

; C.A.Brebbia*

Boundary Elem. Abstr. Newsl., 3(2), p.67 - 70, 1992/03

no abstracts in English

Journal Articles

Dual and multiple reciprocity formulations applied to fission neutron source problems

; C.A.Brebbia*

Boundary Elements XIV, Vol.1; Field Problems and Applications, p.25 - 38, 1992/00

no abstracts in English

Journal Articles

Remedy for round-off error accumulation observed in a neutron diffusion calculation using the multiple reciprocity boundary element method

; C.A.Brebbia*

Engineering Analysis with Boundary Elements, 10, p.345 - 352, 1992/00

 Times Cited Count:9 Percentile:73.03(Engineering, Multidisciplinary)

no abstracts in English

Journal Articles

Boundary element formulation of fission neutron source problems using only boundary integrals

; C.A.Brebbia*

Engineering Analysis with Boundary Elements, 8(5), p.239 - 244, 1991/10

 Times Cited Count:9 Percentile:76.25(Engineering, Multidisciplinary)

no abstracts in English

Journal Articles

Space-dependent core/reflector boundary conditions generated by the boundary element method for pressurized water reactors

; C.A.Brebbia*

Nuclear Science and Engineering, 107, p.246 - 264, 1991/03

 Times Cited Count:15 Percentile:81.67(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Boundary element method applied to neutron diffusion problems of a thin layer sandwiched between two zones

; C.A.Brebbia*

Boundary Elements XII, Vol.1; Applications in Stress Analysis, Potential and Diffusion, p.227 - 239, 1990/00

no abstracts in English

22 (Records 1-20 displayed on this page)