CFD analysis of a cask for spent fuel dry storage: Model fundamentals and sensitivity studies

2015 ◽  
Vol 76 ◽  
pp. 54-62 ◽  
Author(s):  
Luis E. Herranz ◽  
Jaime Penalva ◽  
Francisco Feria
Keyword(s):  
Cfd Analysis ◽  
Spent Fuel ◽  
Storage Model ◽  
Dry Storage ◽  
Sensitivity Studies

scholarly journals The Need for Integrating the Back End of the Nuclear Fuel Cycle in the United States of America

MRS Advances ◽  
2018 ◽  
Vol 3 (19) ◽  
pp. 991-1003 ◽  
Author(s):  
Evaristo J. Bonano ◽  
Elena A. Kalinina ◽  
Peter N. Swift
Keyword(s):  
United States ◽  
Nuclear Fuel ◽  
United States Of America ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Spent Fuel ◽  
Dry Storage ◽  
The Us

ABSTRACTCurrent practice for commercial spent nuclear fuel management in the United States of America (US) includes storage of spent fuel in both pools and dry storage cask systems at nuclear power plants. Most storage pools are filled to their operational capacity, and management of the approximately 2,200 metric tons of spent fuel newly discharged each year requires transferring older and cooler fuel from pools into dry storage. In the absence of a repository that can accept spent fuel for permanent disposal, projections indicate that the US will have approximately 134,000 metric tons of spent fuel in dry storage by mid-century when the last plants in the current reactor fleet are decommissioned. Current designs for storage systems rely on large dual-purpose (storage and transportation) canisters that are not optimized for disposal. Various options exist in the US for improving integration of management practices across the entire back end of the nuclear fuel cycle.

Analysis for seismic response of dry storage facility for spent fuel

2009 ◽  
Vol 239 (1) ◽  
pp. 158-168 ◽  
Author(s):  
Yung-Yen Ko ◽  
Shang-Yi Hsu ◽  
Cheng-Hsing Chen
Keyword(s):  
Seismic Response ◽  
Storage Facility ◽  
Spent Fuel ◽  
Dry Storage

Specific outcomes of the research on the spent fuel long-term evolution in interim dry storage and deep geological disposal

2006 ◽  
Vol 352 (1-3) ◽  
pp. 246-253 ◽  
Author(s):  
C. Ferry ◽  
C. Poinssot ◽  
C. Cappelaere ◽  
L. Desgranges ◽  
C. Jegou ◽  
...  
Keyword(s):  
Long Term Evolution ◽  
Spent Fuel ◽  
Geological Disposal ◽  
Dry Storage ◽  
Term Evolution ◽  
Deep Geological Disposal

Design study of a modular dry storage facility for typical PWR spent fuel

2006 ◽  
Vol 48 (6) ◽  
pp. 487-494 ◽  
Author(s):  
Masood Iqbal ◽  
J. Khan ◽  
Sikander M. Mirza
Keyword(s):  
Storage Facility ◽  
Spent Fuel ◽  
Design Study ◽  
Dry Storage

The Radiation Protection Design of PWR Spent Fuel Dry Storage Facility

2018 ◽  
Author(s):  
Liming Huang ◽  
Shouhai Yang ◽  
Jie Liu
Keyword(s):  
Radiation Protection ◽  
Nuclear Power ◽  
Radiation Safety ◽  
Three Dimensional ◽  
Radiation Shielding ◽  
Storage Facility ◽  
Spent Fuel ◽  
Dry Storage ◽  
Spent Fuel Storage ◽  
Fuel Storage

Radiation safety is an important part of safety assessment of spent fuel dry storage technology. This paper describes the radiation protection design of PWR spent fuel dry storage facility for radiation safety completed by China General Nuclear Power Corporation. Considering the special site conditions, Monte Carlo method is used to complete the precise calculation of the three-dimensional radiation dose field in the spent fuel storage building. Through the spent fuel storage module and the storage building with shielding function, radiation shielding design is completed to meet China’s regulatory requirements, which ensures radiation safety for workers and the public during the transport and storage of spent fuel. It will provide a reference for construction of spent fuel dry storage facility of CPR1000 and HPR1000.

Model of a Dry Storage Facility for a Medium Nuclear Power Plant

2001 ◽  
Author(s):  
Mile Bace ◽  
Kresimir Trontl ◽  
Dubravko Pevec
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radiation Dose ◽  
Dose Rate ◽  
Nuclear Power ◽  
Storage Facility ◽  
Spent Fuel ◽  
Radiation Dose Rate ◽  
Dry Storage ◽  
Fuel Assemblies

Abstract The intention was to model a dry storage facility that could satisfy the needs of a medium nuclear power plant similar to the NPP Krsko. The attention has been focused on radiation dose rate analyses and criticality calculations. Using the SCALE 4.4 code package and modified QAD-CGGP code, we modeled a facility that satisfies the basic criteria for public radiation protection. The capacity of the storage is 1,400 spent fuel assemblies which is adequate for a forty years medium NPP lifetime.

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