서지주요정보
β-열처리 및 산화거동이 질칼로이-4피복관의 미세조직 및 기계적 이방성에 미치는 효과 = Effect of β-heat treatment and oxidation behavior on microstructure and mechanical anisotropy of zircaloy-4 tube
서명 / 저자 β-열처리 및 산화거동이 질칼로이-4피복관의 미세조직 및 기계적 이방성에 미치는 효과 = Effect of β-heat treatment and oxidation behavior on microstructure and mechanical anisotropy of zircaloy-4 tube / 정성훈.
발행사항 [대전 : 한국과학기술원, 1989].
Online Access 제한공개(로그인 후 원문보기 가능)원문

소장정보

등록번호

8000131

소장위치/청구기호

학술문화관(문화관) 보존서고

DNE 8903

휴대폰 전송

도서상태

이용가능(대출불가)

사유안내

반납예정일

리뷰정보

초록정보

A study on the effect of $\beta$-heat treatment on the microstructure and mechanical anisotropy in Zircaloy-4 CANDU type fuel cladding was conducted. The heat treatment at 1000, 1050, 1100 and 1200$^\circ$C on Zircaloy tubing was carried out by employing a high frequency vaccum induction heating method. The crystallographic preferred orientation of the cladding was evaluated by the X-ray measurement and was quantitatively analyzed in terms of Kearns texture number, f. Morphology of second phase particles and $\alpha$-grain of as-received tube were markedly changed by heat treatment. However, they were not much varied by heat treatment temperature conditions. Heat treated Zircaloy tubes exhibited texture changes but the preferred orientation of grains were still remained. With increasing heat treatment temperatures, the 0.2% yield strength decreased but the hoop strength was not much changed because of changes in preferred orientation as well as $\alpha$-plate width. It was found that the texture parameter, f, values of Zircaloy tubes were influenced by the $\beta$-heat treatment concerning $f_l$, $f_r$ and $f_t$ respectively. An equation, Y=145$f_l$ + 320, derived in this study to correlate between 0.2% yield strength and $f_l$ values was found to be agreed well with Ballingers' theory. In addition, an experimental work with SEM confirmed the presence of hard and soft grains in the tensile tested matrix of Zircaloy cladding. A study on the change of mechanical properties and oxidation behavior of Zircaloy-4 fuel cladding after exposing at 900$^\circ$C and 1000$^\circ$C under the steam atomsphere was carried out. The growth of the $ZrO_2$ layer combined with an oxygen-rich $\alpha$-phase layer into the Zircaloy tube material can be described by an expression, $E = 1.1\sqrt{DT}+2\times10^{-4}$. The tensile strength of Zircaloy tubes increased for a short period of exposure time and decreased rapidly with further exposure while the hoop strength did not decreased greatly. In the meantime, the axial and circumferential elongations showed embrittlement phenomena by the drastical decrease with increasing the exposure time.

서지기타정보

서지기타정보
청구기호 {DNE 8903
형태사항 ix, 99 p. : 삽화, 사진 ; 26 cm
언어 한국어
일반주기 저자명의 영문표기 : Sung-Hoon Jung
지도교수의 한글표기 : 김인섭
지도교수의 영문표기 : In-Sup Kim
학위논문 학위논문(박사) - 한국과학기술원 : 핵공학과,
서지주기 참고문헌 : p. 35-43
주제 Microstructure.
Anisotropy.
Nuclear fuel claddings.
원자로 재료. --과학기술용어시소러스
핵 연료. --과학기술용어시소러스
열 처리. --과학기술용어시소러스
Metals --Heat treatment.
QR CODE

책소개

전체보기

목차

전체보기

이 주제의 인기대출도서