scholarly journals Validation of Spent Fuel Dose Rate Calculations Using NDA Measurement Campaign Data

2020 ◽  
Author(s):  
Yan Cao ◽  
Matthew Boyd ◽  
Bo Feng
2019 ◽  
Vol 24 (1) ◽  
pp. 64-70
Author(s):  
Mingliang Xie ◽  
Fei Xie ◽  
Fuchang Shan ◽  
Zhengquan Xie ◽  
Mingrui Li ◽  
...  

Author(s):  
Mile Bace ◽  
Kresimir Trontl ◽  
Dubravko Pevec

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.


2021 ◽  
Vol 11 (16) ◽  
pp. 7362
Author(s):  
Arturas Smaizys ◽  
Ernestas Narkunas ◽  
Gintautas Poskas ◽  
Povilas Poskas

The present SF management concept in Lithuania envisages that spent RBMK-1500 fuel will be stored in dry storage containers for 50 years, before being disposed of in a deep geological repository. However, the risk that a deep geological repository will not be constructed at the planned time should be taken into account, and the extension of SF storage over 50 years should be considered. This paper presents a comparison of gamma and neutron dose rate distributions and variations with planned and extended storage times for cast iron and metal–concrete containers loaded with RBMK-1500 SF. All calculations were performed using the SCALE computer codes system. The modeling results show that the overall shielding properties of the CONSTOR® RBMK-1500 container containing the same neutron and gamma sources are better than those of the CASTOR® RBMK-1500 container. During an extended storage period (from 50 to 300 years), the total dose rate would decrease considerably and the dose rate due to neutrons would become dominant for both containers.


2008 ◽  
Vol 35 (12) ◽  
pp. 2296-2305 ◽  
Author(s):  
A.Y. Chen ◽  
Y.F. Chen ◽  
J.N. Wang ◽  
R.J. Sheu ◽  
Y.-W.H. Liu ◽  
...  

2002 ◽  
Vol 90 (9-11) ◽  
Author(s):  
S. Stroes-Gascoyne ◽  
F. King ◽  
J. S. Betteridge ◽  
F. Garisto

SummaryThe long-term stability of spent nuclear fuel under deep geologic repository conditions will be determined mostly by the influence of α-radiolysis, since the dose-rate for α-radiolysis will exceed that for γ/β-radiolysis beyond a fuel age of ∼100 years and will persist for more than 10000 years. Dissolution rates derived from studies with currently available spent fuel include radiolysis effects from γ/β- as well as α-radiolysis. The use of external α-sources and chemically added H


2011 ◽  
Vol 175 (1) ◽  
pp. 343-350 ◽  
Author(s):  
Y. F. Chen ◽  
R. J. Sheu ◽  
S. H. Jiang ◽  
J. N. Wang ◽  
U. T. Lin

Author(s):  
Masamichi Obata ◽  
Yasushi Ooishi

High dose rate metal waste from core internals, such as BWR channel boxes or control rods are stored in spent fuel pool or site bunker pool. Waste form for final disposal of these high dose rate metal wastes should eliminate water to prevent hydrogen gas generation which can be caused by radiolysis of water. Toshiba’s newly developed drying system for high dose rate metal wastes enable very low content of water even if the waste have a powder layer. Toshiba will provide the total system to fabricate the waste form for high dose rate metal wastes. An operational condition to dry the B4C control rod which is the typical waste with powder layer was estimated based on experimental data.


Author(s):  
Kohtaro UEKI ◽  
Hideo AKIYAMA ◽  
Kazunari ONISHI ◽  
Yoshihiro MATSUMOTO ◽  
Tadashi MASEGAWA ◽  
...  

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