Shielding performance of a newly designed transport cask in the Advanced Conditioning Spent Fuel Pyroprocess Facility

被引：1

作者：

Park, Chang Je ^{[1
]}

Jeong, Chang Joon ^{[1
]}

Min, Deok Ki ^{[1
]}

Kang, Bee Young ^{[1
]}

Choi, Woo Seok ^{[1
]}

Lee, Joo Chan ^{[1
]}

Bang, Gyeoung Sik ^{[1
]}

Seo, Ki Seog ^{[1
]}

机构：

[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2008年 / 40卷 / 04期

关键词：

ACPF; transport cask; shielding calculation;

D O I：

10.5516/NET.2008.40.4.319

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

To transport process wastes efficiently from the Advanced Spent Fuel Conditioning Pyro-process Facility (ACPF) at the Korea Atomic Energy Research Institute (KAERI), a new hot cell cask has been designed based on an existing hot cell padirac transport cask, with not only a neutron absorber for improved shielding capability, but also a docking facility for an easy docking system. In the new hot cell cask, two kinds of materials have been considered as shielding materials, polyethylene and resin. To verify the transport compatibility of the waste and spent fuel for the ACPF, neutron and photon shielding calculations were performed using the MCNPX code. The source term was evaluated by the ORIGEN-ARP code system based on spent PWR fuel. From the calculation, it was found that the maximum surface dose rates of the hot cell cask with the two candidates were estimated within the limit (2 mSv/hr).

引用

页码：319 / 326

页数：8

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