KN-18 spent nuclear fuel transport cask
Creators
- 1. Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of)
Description
KN-18 cask as shown in Fig.1 was designed to transport up to 18 PWR spent nuclear fuel assemblies in compliance with the requirements of Korea and IAEA regulations for Type B(U)F package. It provides containment, radiation shielding, structural integrity, criticality control and heat removal for normal and accident conditions of transportation. CE 16x16 fuel with maximum enrichment of 5.0 wt.%, maximum burnup of 60 GMWD/MTU and minimum cooling time of 9 years can be loaded and transported under both dry and wet conditions. Cask body of a thick forged carbon steel inner shell, a neutron shielding layer and a stainless steel outer shell is closed by two stainless steel lids. Neutron shielding material is installed surrounding the inner shell in the external shell with longitudinal aluminum heat transfer fins. Stainless steel fuel basket with neutron absorbing plates to accommodate 18 PWR fuel assemblies provides support of the fuel, control of criticality and path to dissipate heat. Impact limiters to absorb the impact energy under hypothetical accident conditions are attached at the top and bottom side of the cask during transportation. Carbon steel surfaces were covered by stainless steel cladding for corrosion protection and external cask surfaces were treated by buffing to facilitate decontamination work. Handling weight loaded with fuel is 104 tons and total transportation weight including impact limiters is 126 tons. The cask was licensed in accordance with Korea Nuclear Safety Act. Total four casks were fabricated in accordance with ASME Sec.III Div.3 and legal fabrication examination was undergone. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 18th international symposium on the packaging and transportation of radioactive materials (PATRAM 2016)
- Imprint Pagination
- [6947 p.]
- Journal Page Range
- 6 p.
Conference
- Title
- 18. international symposium on the packaging and transportation of radioactive materials
- Acronym
- PATRAM 2016
- Dates
- 18-23 Sep 2016
- Place
- Kobe, Hyogo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49059724
- Subject category
- S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; CRITICALITY; FUEL ASSEMBLIES; HEAT TRANSFER; HYPOTHETICAL ACCIDENTS; MULTIPLICATION FACTORS; NONDESTRUCTIVE TESTING; PWR TYPE REACTORS; QUALITY ASSURANCE; SHIELDING MATERIALS; SPENT FUEL CASKS; SPENT FUELS; STAINLESS STEELS; URANIUM DIOXIDE; WASTE TRANSPORTATION
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CARBON ADDITIONS; CASKS; CHALCOGENIDES; CONTAINERS; DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUELS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MANAGEMENT; MATERIALS; MATERIALS TESTING; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; QUALITY MANAGEMENT; REACTOR MATERIALS; REACTORS; STEELS; TESTING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as DVD-ROM Data in PDF format. Folder Name: FinalPaper; Paper No. F1004.pdf; 9 refs., 14 figs.