서지주요정보
CANDU 형 핵 연료봉 지지체의 형상 최적 설계 = Shape optimal design of the fuel assembly bearing pad in CANDU reactor
서명 / 저자 CANDU 형 핵 연료봉 지지체의 형상 최적 설계 = Shape optimal design of the fuel assembly bearing pad in CANDU reactor / 이병령.
저자명 이병령 ; Lee, Byung-Ryung
발행사항 [서울 : 한국과학기술원, 1987].
Online Access 원문보기 원문인쇄

소장정보

등록번호

4104602

소장위치/청구기호

학술문화관(문화관) 보존서고

MNE 8710

SMS전송

도서상태

이용가능

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반납예정일

초록정보

It has been reported that crevice corrosion had been created on the bearing pads of fuel bundles and also on the inner surface of pressure tubes in CANDU nuclear power plants. The reasons of the crevice corrosion might be that small local boiling may be occurred in the small cavities between the surfaces of bearing pad and pressure tube, therefore, Lithium, which had been added to coolant for proper chemical characteristics of the coolant, might be concentrated in the cavities. Following have been considered as the methods to solve this crevice corrosion problem. 1. Changes of coolant chemical characteristics. 2. Improvement of coolant flow in the cavities. 3. Reduction of heat flux from bearing pad surface to pressure tube inner surface by changing the shape of bearing pad. But the first two methods (1 and 2) are thought to affect various effects to primary coolant system and may be difficult to actually perform. And the third method has been considered a desirable and practical method to reduce or eliminate the crevice corrosion, especially because it is known that below a certain threshold temperature, the crevice corrosion may not be occurred. Some intuitional methods to optimize the bearing pad shape have been suggested but any analytical and systematic research has not been reported. In this paper, optimal design of bearing pad shape using finite element method has been done by simultaneously considering the reduction of the heat flux from bearing pad surface to pressure tube internal surface and the limitation of stress on the bearing pad within the allowable stress. On the optimal designed bearing pad shape, the average temperature of the surface is lower than the average temperature of currently using shape's surface by about 10℃, any stress concentration is not occurred and all stresses on the bearing pad are fallen within allowable stress limit. In this optimal design work, matrix variational method and adjoint variable technique were used to reduce computing time and computer memory capability, to simplify the variables mathematical relationships and to achieve high accuracy on design sensitivity analysis. The results are very satisfactory. More accurate results are expected if isoparametric element and auto-mesh generation are adopted for the performance of finite element analysis, while triangle elements and uniform mesh generation method were adopted in this work.

서지기타정보

서지기타정보
청구기호 {MNE 8710
형태사항 ix, 47 p. : 삽도 ; 26 cm
언어 한국어
일반주기 저자명의 영문표기 : Byung-Ryung Lee
지도교수의 한글표기 : 전문헌
공동교수의 한글표기 : 장순흥
지도교수의 영문표기 : Moon-Hyun Chun
공동교수의 영문표기 : Soon-Heung Chang
학위논문 학위논문(석사) - 한국과학기술원 : 핵공학과,
서지주기 참고문헌 : p. 46-47
주제 Nuclear fuel rods.
Optimal designs (Statistics)
CANDU 원자로. --과학기술용어시소러스
핵연료 집합체. --과학기술용어시소러스
최적 설계. --과학기술용어시소러스
Pressurized water reactors.
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