Initial relocation behavior of control rod materials in boiling water reactors studied via time-resolved visualization-Reference-Cited by-同舟云学术

Initial relocation behavior of control rod materials in boiling water reactors studied via time-resolved visualization

Published:2018-07 Issue: Volume:333 Page:99-114
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ueda Shota^ORCID,Jo Byeongnam,Kondo Masahiro,Erkan Nejdet,Yajima Takeshi,Okamoto Koji

Funder

JSPS

Ministry of Education, Culture, Sports, Science and Technology of Japan

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference18 articles.

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3. Gauntt, R.O., Gasser, R.D., 1990. Results of the DF-4 BWR control blade-channel box test. In: Prc. Eighteenth Water Reactor Safety Information Meeting, NUREG/CP-0114, vol. 2, pp. 25–40.

4. Gauntt, R.O., Gasser, R.D., Ott, L.J., 1989. The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box. Sandia National Laboratory, USA, Report NUREG/CR-4671.

5. Towards a better understanding of iodine chemistry in RCS of nuclear reactors;Girault;Nucl. Eng. Des.,2009

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