Aspects of Bending High-Borated Austenitic Stainless Steel Sheets for Interim Storage of Spent Nuclear Fuel

Author:

Odehnal Josef1ORCID,Studecký Tomáš2ORCID,Čejková Petra1,Poláková Ivana2,Rund Martin2,Brunát Václav2,Martínek Petr2,Francisko Pavel1,Donik Črtomir3ORCID

Affiliation:

1. Department of Material Science and Technology, Faculty of Mechanical Engineering, University of West Bohemia, UWB Plzeň, Univerzitní 22, 306 14 Pilsen, Czech Republic

2. COMTES FHT a.s., Průmyslová 995, 334 41 Dobřany, Czech Republic

3. Department of Physics and Chemistry of Materials, IMT-Institute of Metals and Technology, Lepi Pot 11, 1000 Ljubljana, Slovenia

Abstract

The presented work is aimed at the evaluation of the cold bending capacity of high-borated austenitic stainless steel sheets. Due to their excellent neutron-absorbing capability, borated stainless steels belong to the group of tailor-made structural materials widely used for vertical storage baskets for holding spent nuclear fuel assemblies in cooling pools at dry or wet storage facilities. The basket consists of individual fuel assembly cells. Each polygonal cell is usually welded from several steel strips. It would be advantageous to use bent steel semi-product to avoid welded seams as much as possible. Welded seams are difficult to make, and moreover, they are susceptible to corrosion. However, high-borated stainless steels, because of their boron content, show limited hot and cold workability. Thus, their cold bending capacity would be the primary issue. Their austenitic matrix with embedded hard and brittle boride particles is prone to the evolution and fast propagation of dimple transgranular fracture. This work is focused on the bending aspects of borated steel sheets with respect to the most commonly used hexagonal cell geometry. Experimental results provide practical recommendations for the rack design. The damage criterion has also been proposed using FEM simulations in DEFORM®.

Funder

ERDF Research of advanced steels with unique properties

Publisher

MDPI AG

Subject

General Materials Science,Metals and Alloys

Reference28 articles.

1. IAEA (1982). IAEA Technical Report No. 218—Storage of Water Reactor Spent Fuel in Water Pools, IAEA. No. 218.

2. Committee on the Safety and Security of Commercial Spent Nuclear Fuel Storage, Board on Radioactive Waste Management (2006). Safety and Security of Commercial Spent Nuclear, Illustrate, National Academies Press.

3. Neutron Effects on Borated Stainless Steel;Soliman;Nucl. Technol.,1991

4. Nuclear radiation shielding effectiveness and corrosion behavior of some steel alloys for nuclear reactor systems;Sadawy;Def. Technol.,2019

5. Stanisz, P., Oettingen, M., and Cetnar, J. (2022). Development of a Trajectory Period Folding Method for Burnup Calculations. Energies, 15.

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3