scholarly journals Scoping design analyses for optimized shipping casks containing 1-, 2-, 3-, 5-, 7-, or 10-year-old PWR spent fuel

1983 ◽  
Author(s):  
J.A. Bucholz
Keyword(s):  
1991 ◽  
Vol 113 (4) ◽  
pp. 522-529 ◽  
Author(s):  
S. M. Cho ◽  
A. H. Seltzer ◽  
M. Blackbourn

A passive, natural thermosyphon, air-cooled modular vault dry store (MVDS) system is being constructed for the storage of nuclear spent fuel for the Fort St. Vrain (FSV) Nuclear Power Station. In support of this FSV-MVDS system, thermal-hydraulic design analyses have been performed. The objective of the analyses is to determine flow and temperature distributions within the system and thus to ensure that the maximum fuel element temperatures shall not exceed specified design limit values under various loading and unloading conditions. This paper presents the method of analysis and discusses the resulting thermal-hydraulic characteristics of the MVDS system.


Equipment ◽  
2006 ◽  
Author(s):  
D. Sujish ◽  
C. Meikandamurthy ◽  
T. R. Ellappan ◽  
M. Rajan ◽  
G. Vaidyanathan

1982 ◽  
Author(s):  
E. DRAPER ◽  
GEORGE COULBOURN
Keyword(s):  

Kerntechnik ◽  
2020 ◽  
Vol 85 (1) ◽  
pp. 38-53
Author(s):  
M. J. Leotlela ◽  
I. Petr ◽  
A. Mathye

1989 ◽  
Author(s):  
J. H. Jo ◽  
P. F. Rose ◽  
S. D. Unwin ◽  
V. L. Sailor ◽  
K. R. Perkins ◽  
...  
Keyword(s):  

Sensors ◽  
2021 ◽  
Vol 21 (8) ◽  
pp. 2630
Author(s):  
Luigi Cosentino ◽  
Quentin Ducasse ◽  
Martina Giuffrida ◽  
Sergio Lo Meo ◽  
Fabio Longhitano ◽  
...  

In the framework of the MICADO (Measurement and Instrumentation for Cleaning And Decommissioning Operations) European Union (EU) project, aimed at the full digitization of low- and intermediate-level radioactive waste management, a set of 32 solid state thermal neutron detectors named SiLiF has been built and characterized. MICADO encompasses a complete active and passive characterization of the radwaste drums with neutrons and gamma rays, followed by a longer-term monitoring phase. The SiLiF detectors are suitable for the monitoring of nuclear materials and can be used around radioactive waste drums possibly containing small quantities of actinides, as well as around spent fuel casks in interim storage or during transportation. Suitable polyethylene moderators can be exploited to better shape the detector response to the expected neutron spectrum, according to Monte Carlo simulations that were performed. These detectors were extensively tested with an AmBe neutron source, and the results show a quite uniform and reproducible behavior.


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