Proceedings of the Workshop on Reactor Safety Research, Focusing on the Integrity of Aged Components; March 17, 2003, Tokai Research Establishment, Tokai-mura

Hidaka, Akihide; Suzuki, Masahide

JAERI-Conf 2003-014, 178 Pages, 2003/09

JAERI-Conf-2003-014.pdf:19.17MB

The Workshop on Reactor Safety Research focusing on the integrity of aged components was held at the Tokai Research Establishment on March 17, 2003. The purpose of the Workshop was to obtain useful information to proceed with the reactor safety research in future and to resolve the issues on the integrity evaluation of aged components through the discussions followed by the presentations on the results of the research at JAERI on all the research subjects assigned to JAERI in the Five-Year Program of Safety Research for Nuclear Installations established by the Nuclear Safety Commission, and on those of the studies at JAERI on the integrity of core shrouds of BWR plants. Thirty-eight people from outside JAERI including the press such as Nihon Television Network Corporation and Shin-Ibaraki Shinbun and fifty-seven people from JAERI attended the Workshop. This proceeding compiles all the viewgraphs presented in the workshop, the opinions of participants for forum and the answers, and summary of questionnaire on workshop.

Influence of thermal properties of zirconia shroud on analysis of PHEBUS FPTO bundle degradation test with ICARE2 code

Hidaka, Akihide; Nakamura, Jinichi; Sugimoto, Jun

Nucl. Eng. Des., 168(1-3), p.361 - 371, 1997/00

https://doi.org/10.1016/S0029-5493(96)00009-X

no abstracts in English

Analysis report on test of tubesheet model of evaporator

Kasahara, Naoto; Horikiri, Morito; Iwata, Koji; Uno, Tetsuro*; Imazu, Akira; Tokura, Sunao*

PNC TN9410 87-057, 245 Pages, 1987/03

PNC-TN9410-87-057.pdf:33.69MB

The structural design methods for tubesheets have been studied in connection with the development of fast breeder reactors, because tubesheet structures have complex and 3-dimmensional configulation, and are subjected to severe thermal loading. In Japan the tentative guidelines for structural design methods for tubesheets of FBR plants are proposed by the task group on the design methods of tubesheets in Power Reactor and Nuclear Fuel Development Corporation. The objective of this study is to validate this tentative methods by using data obtained from thermal transient tests of tubesheet models of evaporator and detailed analytical study, and moveover to provide usuful knowledge to rationalize the tentative guidelines. In this report, simplified methods of thermal and stress analyses for tubesheet structures are newly proposed and applied to thermal transient tests of tubesheet models which were carried out in 1984. The works contained in this report are summarized as; (1)Heat transfer analyses with 3-dimensional full model and elastic analyses with the same model are executed on the tubesheet structure, and the mechanism of thermal stress generation in the tubesheets is clarified. (2)Two simplified heat transfer analysis models are developed: the convection film model and the modified perforated plate model. Tbose models are proved to be accurate enough through the comparison with the results of 3-dimensional analyses. (3)Heat-transfer coefficient on the tubesheet structures are discussed with the data of temperature tests and thermal-hydraulicanalyses. As the results, it is shown that the film heat-transfer formula for turbulent flow inside tubes canbe used conservatively for inner surface of shrouds. (4)The simplified inelastic analysis method for tubesheets is developed. This method uses 2-dimensional models considering 3-dimensional effects of shrouds. As the results of comparison with the thermal transient test data of tubesheet model, the ...