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Journal Articles

Inherent core safety performance of small sodium-cooled fast reactor with oxide fuel

Takano, Kazuya; Oki, Shigeo; Doda, Norihiro; Chikazawa, Yoshitaka; Maeda, Seiichiro

Proceedings of 2023 International Congress on Advanced in Nuclear Power Plants (ICAPP 2023) (Internet), 7 Pages, 2023/04

The MOX fueled SMR-SFRs with lower linear heat rating of 100 W/cm and 50 W/cm, whereas the linear heat rating at rated power is around 400 W/cm in general, were designed to decrease the fuel temperature during its rated power state in order to pursue the inherent core safety for MOX fueled SMR-SFRs. The transient analyses for Anticipated Transient Without Scram (ATWS) events represented by an Unprotected Loss of Flow (ULOF) accident on the lower linear heat rating cores were performed considering their inherent feedback reactivity. Through the transient analysis, the inherent core safety performances for the lower linear heat rating cores were discussed based on the evaluated maximum coolant temperature and Cumulative Damage Fraction (CDF) as criteria to maintain the core and fuel integrity. The feasible design window for MOX fueled SMR-SFRs with the inherent core safety focusing on the linear heat rating was identified based on the transient analysis results.

JAEA Reports

None

Funasaka, Hideyuki; ;

JNC TN1200 2001-002, 209 Pages, 2001/01

JNC-TN1200-2001-002.pdf:7.84MB

no abstracts in English

JAEA Reports

A Design study on a large FBR plant enhancing passive safety

Hayashi, Hideyuki; ;

PNC TN9410 96-062, 186 Pages, 1996/02

PNC-TN9410-96-062.pdf:5.83MB

A conceptual design study on a 1300MWe large FBR plant was performed with focusing on enhancing passive safety and capital cost reduction. Spectrum-adjusted mixed nitride fueled core in which zirconium hydride was added, was applied to enlarge Doppler reactivity coefficient. Breeding ratio of 1.2 was obtained only with one layer of radial blanket subassemblies by optimizing the content of the zirconium hydride. The optimization also lightened the burden to the reactor structure through the reduction of the core diameter. Reactor passive shutdown were performed in the ATWS events of ULOF and ULOHS, and UTOP caused by one control rod full runout was endurable under the criterion of the prevention of coolant boiling. The safety feature can be called as inherent safety, because the feature comes only from the reactivity characteristics of the core. The integrities of the reactor structures which characterize head-access loop type reactor were evaluated on the transient thermal stress at the loss of flow accident and on seismic strain. Vertical strain of core support plate at loss of flow condition was also evaluated on the passive shutdown at ULOF. The capital cost of the large FBR plant was estimated 1.3 to 1.4 times as high as that of the same scale LWR based on the weight of major components.

JAEA Reports

Explanation on the new options and extensions of FINAS updated version 13.0

Tsukimori, Kazuyuki;

PNC TN9460 95-004, 211 Pages, 1995/12

PNC-TN9460-95-004.pdf:7.59MB

This report describes the explanation on the new options and extensions of "FINAS" (FInite Element Nonlinear Structural Analysis System) updated version 13.0 (developed from April 1993 to July 1995). The items are as follows. (1)3 kinds of spring-supported base elements (2)4-node quadrilateral plane strain element (3)Off-set function utilized with 3-dimensional beam element (4)Definition of centrifugal force by angular velocity and pivot (5)2-node heat flow element for thermal hydraulic analysis (6)Addition of CQC method and ABS method as mode superposition method for spectrum response analysis (7)Addition of logarithmic interpolation as spectrum data interpolation method for spectrum response analysis (8)*Multi-point input function of spectrum data in spectrum response analysis (9)Output function of maximum reaction force in spectrum response analysis (10)Output function of member forces for shell element and bar element (11)Plotting function of normal stresses and shear stresses in the vectorial plot charts (12)Plotting function of user-defined state variables in the analysis by an arbitrary constitutive equation (13)**Scaling function in X-Y plane plotting function (14)Improvement of calculation efficiency in surface contact analysis (15)Addition of Sloan's argorithmin in renumber function (16)Calculation function of all eigenvalues in the analysis of structure system (17)Extension of the limit of maximum degrees of freedom (up to 4,000,000) (18)**Provision of user's subroutine for the arbitrary constitutive equation (19)**Provision of user's subroutine for the arbitrary element (20)Extension of two-surface cyclic plasticity model by introducing temperature dependency (21)Revision of execusion commands and monitering function of statistical information in UNIX environment (22)Automatic verification system in UNIX environment (23)Guide of utility programs supporting the development of FINAS (EWS version) The properties of new functions were verified ...

Journal Articles

Future prospects of high temperature gas cooled reactor

Tobioka, Toshiaki

Denki Kyokai Zasshi, 0(840), p.21 - 27, 1993/10

no abstracts in English

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