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

2020 ◽  
Author(s):  
Yan Cao ◽  
Matthew Boyd ◽  
Bo Feng
Keyword(s):  
Dose Rate ◽  
Spent Fuel ◽  
Measurement Campaign

Estimation of the Dose Rate of Spent Fuel-Related Components of Lingao Nuclear Power Plant Using ORIGEN2 and MCNP5

2019 ◽  
Vol 24 (1) ◽  
pp. 64-70
Author(s):  
Mingliang Xie ◽  
Fei Xie ◽  
Fuchang Shan ◽  
Zhengquan Xie ◽  
Mingrui Li ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dose Rate ◽  
Nuclear Power ◽  
Spent Fuel

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.

scholarly journals Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal—Concrete Casks Used for RBMK-1500 Spent Fuel Storage

2021 ◽  
Vol 11 (16) ◽  
pp. 7362
Author(s):  
Arturas Smaizys ◽  
Ernestas Narkunas ◽  
Gintautas Poskas ◽  
Povilas Poskas
Keyword(s):  
Cast Iron ◽  
Dose Rate ◽  
Storage Period ◽  
Neutron Dose ◽  
Deep Geological Repository ◽  
Spent Fuel ◽  
Geological Repository ◽  
Fuel Storage ◽  
Management Concept ◽  
Neutron Dose Rate

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.

A comparison of dose rate calculations for a spent fuel storage cask by using MCNP and SAS4

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 ◽  
...  
Keyword(s):  
Dose Rate ◽  
Spent Fuel ◽  
Spent Fuel Storage ◽  
Fuel Storage

The effects of alpha-radiolysis on UO2 dissolution determined from electrochemical experiments with 238Pu-doped UO2

2002 ◽  
Vol 90 (9-11) ◽  
Author(s):  
S. Stroes-Gascoyne ◽  
F. King ◽  
J. S. Betteridge ◽  
F. Garisto
Keyword(s):  
Dose Rate ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Spent Fuel ◽  
Geologic Repository ◽  
Dissolution Rates ◽  
Term Stability ◽  
Long Term Stability ◽  
Alpha Radiolysis

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

Surface Dose Rate Calculations of a Spent-Fuel Storage Cask by Using MAVRIC and Its Comparison with SAS4 and MCNP

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

Advanced Drying System to Meet Radiolysis Criteria of Metallic Waste

2011 ◽  
Author(s):  
Masamichi Obata ◽  
Yasushi Ooishi
Keyword(s):  
Dose Rate ◽  
High Dose Rate ◽  
Hydrogen Gas ◽  
Waste Form ◽  
Powder Layer ◽  
High Dose ◽  
Total System ◽  
Spent Fuel ◽  
Drying System ◽  
Metal Wastes

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.

Measurement of Dose Rate Distributions in the Spent Fuel Transport Vessel "ROKUEI MARU" and Monte Carlo Analysis

2002 ◽  
Vol 2002.8 (0) ◽  
pp. 457-460
Author(s):  
Kohtaro UEKI ◽  
Hideo AKIYAMA ◽  
Kazunari ONISHI ◽  
Yoshihiro MATSUMOTO ◽  
Tadashi MASEGAWA ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Dose Rate ◽  
Monte Carlo Analysis ◽  
Spent Fuel ◽  
Transport Vessel
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