2016
DOI: 10.17146/aij.2016.585
|View full text |Cite
|
Sign up to set email alerts
|

Characterization of Zircaloy-4 after Gaseous Hydriding at the Temperature Range of 350-600<sup>°</sup>C

Abstract: The degradation of the mechanical properties of zircaloy-4 as nuclear fuel cladding is inevitable due to its interaction with hydrogen during normal reactor operation. This experiment observed the occurence of hydride phases after gaseous hydriding with hydrogen at elevated temperature, and their effects were evaluated based on the material's microstructure and mechanical properties. The zircaloy-4 cladding materials were annealed for two hours. It was followed by hydriding with the pressure from 100 up to 120… Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1
1

Citation Types

0
0
0
2

Year Published

2017
2017
2018
2018

Publication Types

Select...
2

Relationship

0
2

Authors

Journals

citations
Cited by 2 publications
(2 citation statements)
references
References 16 publications
0
0
0
2
Order By: Relevance
“…Potongan kelongsong Zr-2 dan Zr-4 dipanaskan pada temperatur 500°C dalam tabung sampel yang terintegrasi dengan tungku sistem hydridingdehydriding [13]. Proses pemanasan berada dalam kondisi vakum dengan tekanan vakum mencapai orde 10 -2 mbar selama 1 jam.…”
Section: Pendahuluanunclassified
“…Potongan kelongsong Zr-2 dan Zr-4 dipanaskan pada temperatur 500°C dalam tabung sampel yang terintegrasi dengan tungku sistem hydridingdehydriding [13]. Proses pemanasan berada dalam kondisi vakum dengan tekanan vakum mencapai orde 10 -2 mbar selama 1 jam.…”
Section: Pendahuluanunclassified
“…Penelitian ini menggunakan kelongsong Zr-4 non iradiasi yang biasa digunakan di reaktor tipe PWR (Power Water Reactor) dengan komposisi kimia dalam persen berat Zr 98,27%, Sn 1,4%, Fe 0,21% dan Cr 0,12% [12]. Kelongsong Zr-4 mempunyai diameter luar 13,25 mm, ketebalan 0,45 mm dan panjang 50 mm.…”
Section: Metodologiunclassified