Heat removal verification tests of full-scale concrete casks under accident conditions-Reference-Cited by-同舟云学术

Heat removal verification tests of full-scale concrete casks under accident conditions

Published:2008-05 Issue:5 Volume:238 Page:1206-1212
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Wataru Masumi,Takeda Hirofumi,Shirai Koji,Saegusa Toshiari

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

Reference5 articles.

1. Creer, J.M., 1987. The TN-24P PWR spent-fuel dry storage cask: testing and analyses. PNL-6054.

2. JSME, 2003. Code for Construction of Spent Nuclear Fuel Storage Facilities—Rules on Concrete Casks, Canister Transfer Machines and Canister Transport Casks for Spent Nuclear Fuel—JSME S FB1-2003.

3. Sakai, M.T., 2002. Concrete storage cask for interim storage of spent nuclear fuel—evaluation of thermal performance, IHI technical report, vol. 42, no.1, pp. 47–55.

4. Tsuji, H., 2003. Thermal evaluation method for concrete cask is established by full-scale mock-up tests. MES technical report, No. 180, pp. 37–42.

5. Yamakawa, H., 1992. Establishment of cask storage method for storing spent fuel. CRIEPI report U92038.

Cited by 12 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A numerical investigation of an indoor dry storage facility on heat transfer;Annals of Nuclear Energy;2024-02

2. Risk assessment and numerical analysis of short-term accident scenarios in a nuclear fuel storage vault;Numerical Heat Transfer, Part A: Applications;2023-07-06

3. Performance of different duct-nozzle arrangement on heat removal from a nuclear fuel storage vault under regular operating conditions;Nuclear Engineering and Design;2022-08

4. Numerical analysis of forced convection heat transfer in a nuclear fuel storage vault;International Journal of Thermal Sciences;2022-03

5. Numerical investigation for the spent fuel storage building design of the Chinshan nuclear plant;Progress in Nuclear Energy;2021-05