Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Consolidation of spent nuclear fuel rods is being considered as one option for more efficient and compact storage of reactor spent fuel assemblies. In this concept, rods from two disassembled spent fuel assemblies will be consolidated in a space originally intended to store a single unconsolidated assembly. The thermal performance of consolidated fuel rods in dry storage, especially in multiassembly storage systems, is one of the major issues that must be addressed prior to implementation. In this study, Pacific Northwest Laboratory researchers performed thermal-hydraulic analyses for both the REA 2023 cask and the CASTOR-1C cask containing either unconsolidated or consolidated BWR spent fuel assemblies. The objective was to determine the effect of consolidating spent fuel assemblies on the temperature distributions within both types of casks. Two major conclusions resulted from this study. First, a lumping technique (combining rods and flow channels), which reduces the number of computational nodes required to model complex multiassembly geometries, could be used for both unconsolidated and consolidated rods with negligible effect on prediction accuracies. Second, with a relatively high thermal conductivity backfill gas (e.g., helium), the predicted peak fuel rod temperature in a canister of consolidated rods generating the same amount of heat as an unconsolidated assembly is essentially the same as the peak temperature in the unconsolidated assembly. In contrast, with a relatively low thermal conductivity backfill gas (e.g., nitrogen), the opposite is true and the predicted peak temperature in a consolidated canister is significantly higher than in an unconsolidated assembly. Therefore, when rods are consolidated, selection of the backfill gas is important in maintaining peak rod temperatures below allowable values for rods with relatively high decay heat generation rates.
COBRA-SFS (Spent-Fuel Storage) Thermal-hydraulic Analyses of the CASTOR-1C and REA 2023 BWR Storage Casks Containing Consolidated Spent Fuel
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Consolidation of spent nuclear fuel rods is being considered as one option for more efficient and compact storage of reactor spent fuel assemblies. In this concept, rods from two disassembled spent fuel assemblies will be consolidated in a space originally intended to store a single unconsolidated assembly. The thermal performance of consolidated fuel rods in dry storage, especially in multiassembly storage systems, is one of the major issues that must be addressed prior to implementation. In this study, Pacific Northwest Laboratory researchers performed thermal-hydraulic analyses for both the REA 2023 cask and the CASTOR-1C cask containing either unconsolidated or consolidated BWR spent fuel assemblies. The objective was to determine the effect of consolidating spent fuel assemblies on the temperature distributions within both types of casks. Two major conclusions resulted from this study. First, a lumping technique (combining rods and flow channels), which reduces the number of computational nodes required to model complex multiassembly geometries, could be used for both unconsolidated and consolidated rods with negligible effect on prediction accuracies. Second, with a relatively high thermal conductivity backfill gas (e.g., helium), the predicted peak fuel rod temperature in a canister of consolidated rods generating the same amount of heat as an unconsolidated assembly is essentially the same as the peak temperature in the unconsolidated assembly. In contrast, with a relatively low thermal conductivity backfill gas (e.g., nitrogen), the opposite is true and the predicted peak temperature in a consolidated canister is significantly higher than in an unconsolidated assembly. Therefore, when rods are consolidated, selection of the backfill gas is important in maintaining peak rod temperatures below allowable values for rods with relatively high decay heat generation rates.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Consolidation of spent nuclear fuel rods is being considered as one option for more efficient and compact storage of reactor spent fuel assemblies. In this concept, rods from two disassembled spent fuel assemblies will be consolidated in a space originally intended to store a single unconsolidated assembly. The thermal performance of consolidated fuel rods in dry storage, especially in multiassembly storage systems, is one of the major issues that must be addressed prior to implementation. In this study, Pacific Northwest Laboratory researchers performed thermal-hydraulic analyses for both the REA 2023 cask and the CASTOR-1C cask containing either unconsolidated or consolidated BWR spent fuel assemblies. The objective was to determine the effect of consolidating spent fuel assemblies on the temperature distributions within both types of casks. Two major conclusions resulted from this study. First, a lumping technique (combining rods and flow channels), which reduces the number of computational nodes required to model complex multiassembly geometries, could be used for both unconsolidated and consolidated rods with negligible effect on prediction accuracies. Second, with a relatively high thermal conductivity backfill gas (e.g., helium), the predicted peak fuel rod temperature in a canister of consolidated rods generating the same amount of heat as an unconsolidated assembly is essentially the same as the peak temperature in the unconsolidated assembly. In contrast, with a relatively low thermal conductivity backfill gas (e.g., nitrogen), the opposite is true and the predicted peak temperature in a consolidated canister is significantly higher than in an unconsolidated assembly. Therefore, when rods are consolidated, selection of the backfill gas is important in maintaining peak rod temperatures below allowable values for rods with relatively high decay heat generation rates.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1284
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1284
Book Description
Radioactive Waste Management
Author:
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 622
Book Description
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 622
Book Description
Radioactive Waste Management
Author: James Saling
Publisher: Routledge
ISBN: 1351419986
Category : Technology & Engineering
Languages : en
Pages : 430
Book Description
This reviews sources of radioactive waste and introduces radioactive decay and radiation shielding calculations. It covers technical and regulatory aspects of waste management with discussion questions at the end of each chapter to provide an opportunity to explore the many facets of waste management issues. An extensive reference list at the end of each chapter retains the references from the first edition of the book and incorporates references used in preparing this revised text, giving readers an opportunity to look at historical records as well as current information.
Publisher: Routledge
ISBN: 1351419986
Category : Technology & Engineering
Languages : en
Pages : 430
Book Description
This reviews sources of radioactive waste and introduces radioactive decay and radiation shielding calculations. It covers technical and regulatory aspects of waste management with discussion questions at the end of each chapter to provide an opportunity to explore the many facets of waste management issues. An extensive reference list at the end of each chapter retains the references from the first edition of the book and incorporates references used in preparing this revised text, giving readers an opportunity to look at historical records as well as current information.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 596
Book Description
Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 596
Book Description
Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.
INIS Atomindex
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1214
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1214
Book Description
Government Reports Announcements & Index
Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 1224
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 1224
Book Description
Government Reports Annual Index
Author:
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 964
Book Description
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 964
Book Description
Government Reports Annual Index: Keyword A-L
Author:
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 1060
Book Description
Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 1060
Book Description
COBRA-SFS Thermal Analysis of a Sealed Storage Cask for the Monitored Retrievable Storage of Spent Fuel
Author: David R. Rector
Publisher:
ISBN:
Category :
Languages : en
Pages : 35
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 35
Book Description