東華大學圖書館 |

Language: English

Help

回圖書館首頁

手機版館藏查詢

Back

Switch To: Labeled | MARC Mode | ISBD

Design of an experiment that simulat...

Araya, Pablo E.

Linked to FindBook

Google Book

Amazon

博客來

Design of an experiment that simulates spent nuclear fuel within transport casks.

Record Type:	Language materials, printed : Monograph/item
Title/Author:	Design of an experiment that simulates spent nuclear fuel within transport casks./
Author:	Araya, Pablo E.
Description:	201 p.
Notes:	Adviser: Miles Greiner.
Contained By:	Masters Abstracts International45-05.
Subject:	Engineering, Mechanical. -
Online resource:	http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=1442846

Design of an experiment that simulates spent nuclear fuel within transport casks.
Araya, Pablo E.

Design of an experiment that simulates spent nuclear fuel within transport casks. - 201 p.

Adviser: Miles Greiner.

Thesis (M.S.)--University of Nevada, Reno, 2007.

Spent nuclear fuel assemblies are placed within the basket structure of a thick walled cask for transport. The fuel rods generate heat from radioactive decay and the cask must dissipate this heat to the surroundings through the package walls. A goal of a transport package designer is to make sure that fuel rod cladding temperatures do not exceed the containment integrity limit. Therefore cask design is focused on maximizing the number of assemblies contained without surpassing the allowed temperature limit. Conservatism and uncertainty in the thermal analysis therefore leads to under-loading casks, increasing the number of shipments needed and increased public safety hazards. This work details the use of computational fluid dynamics (CFD) simulation software to help design an experiment that will be used to develop better thermal characterization models of spent nuclear fuel. The CFD code is benchmarked with previous experimental data, and is later used to establish key characteristics in the design of an experimental test rig. Simulations results show that geometric simplifications to the test rig can be made and also point to key characteristics that need to be addressed. The experiment design is then presented and will be used for future thermal measurements. The experimental data will be used in the future to develop thermal models of spent nuclear fuel assemblies under normal transport conditions.Subjects--Topical Terms:

783786
Engineering, Mechanical.

Design of an experiment that simulates spent nuclear fuel within transport casks.
LDR:02255nam 2200265 a 45 001 958868
005 20110704
008 110704s2007 ||||||||||||||||| ||eng d
035 $a (UMI)AAI1442846
035 $a AAI1442846
040 $a UMI $c UMI
100 1 $a Araya, Pablo E. $3 1282330
245 1 0 $a Design of an experiment that simulates spent nuclear fuel within transport casks.
300 $a 201 p.
500 $a Adviser: Miles Greiner.
500 $a Source: Masters Abstracts International, Volume: 45-05, page: 2630.
502 $a Thesis (M.S.)--University of Nevada, Reno, 2007.
520 $a Spent nuclear fuel assemblies are placed within the basket structure of a thick walled cask for transport. The fuel rods generate heat from radioactive decay and the cask must dissipate this heat to the surroundings through the package walls. A goal of a transport package designer is to make sure that fuel rod cladding temperatures do not exceed the containment integrity limit. Therefore cask design is focused on maximizing the number of assemblies contained without surpassing the allowed temperature limit. Conservatism and uncertainty in the thermal analysis therefore leads to under-loading casks, increasing the number of shipments needed and increased public safety hazards. This work details the use of computational fluid dynamics (CFD) simulation software to help design an experiment that will be used to develop better thermal characterization models of spent nuclear fuel. The CFD code is benchmarked with previous experimental data, and is later used to establish key characteristics in the design of an experimental test rig. Simulations results show that geometric simplifications to the test rig can be made and also point to key characteristics that need to be addressed. The experiment design is then presented and will be used for future thermal measurements. The experimental data will be used in the future to develop thermal models of spent nuclear fuel assemblies under normal transport conditions.
590 $a School code: 0139.
650 4 $a Engineering, Mechanical. $3 783786
650 4 $a Engineering, Nuclear. $3 1043651
690 $a 0548
690 $a 0552
710 2 $a University of Nevada, Reno. $3 626634
773 0 $t Masters Abstracts International $g 45-05.
790 $a 0139
790 1 0 $a Greiner, Miles, $e advisor
791 $a M.S.
792 $a 2007
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=1442846