The Variation of CANDU Spent Fuel Characteristics During Surface Storage

CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL. There are several options of nuclear fuel utilisation in the HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE). Although mainly RDE utilises low enriched uranium (LEU)-based fuel, which is the most viable option at the moment, it is possible for RDE to utilise other fuel, for example thorium-based and possibly even plutonium-based fuel. Different fuel yields different spent fuel characteristics, so it is necessary to identify the characteristics to understand and evaluate their handling and interim storage. This paper provides the study on the characteristics of thorium-fuelled RDE spent fuel, assuming typical operational cycle. ORIGEN2.1 code is employed to determine the spent fuel characteristics. The result showed that at the end of the calculation cycle, each thorium-based spent fuel pebble generates around 0,627 Watts of heat, 28 neutrons/s, 8.28x1012 photons/s and yield 192.53 curies of radioactivity. These higher radioactivity and photon emission possibly necessitate different measures in spent fuel management, if RDE were to use thorium-based fuel. Tl-208 activity, which found to be emitting potentially non-negligible strong gamma emission, magnified the requirement of proper spent fuel handling especially radiation shielding in spent fuel cask.Keywords: RDE, spent fuel, thorium, HTGR, Tl-208.

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Core Design, Spent-Fuel Characteristics Assessment, and Fuel Cycle Analysis for Thorium-Uranium Breeding Recycle in Pressurized Water Reactors

Nuclear Technology ◽

10.13182/nt13-a19420 ◽

2013 ◽

Vol 183 (3) ◽

pp. 308-320

Author(s):

Guangwen Bi ◽

Shengyi Si ◽

Chanyun Liu

Keyword(s):

Fuel Cycle ◽

Pressurized Water Reactors ◽

Spent Fuel ◽

Pressurized Water ◽

Fuel Cycle Analysis ◽

Fuel Characteristics ◽

Water Reactors

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Spent Fuel Characteristics & Disposal Considerations

Actinides and the Environment ◽

10.1007/978-94-017-0615-5_16 ◽

1998 ◽

pp. 245-265

Author(s):

V. M. Oversby

Keyword(s):

Spent Fuel ◽

Fuel Characteristics

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Characteristics of the Spent Fuel Generated in Korea

ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 1 ◽

10.1115/icem2009-16227 ◽

2009 ◽

Author(s):

Donghak Kook ◽

Jongwon Choi ◽

Heuijoo Choi ◽

Dongkeun Cho

Keyword(s):

Nuclear Power ◽

Storage Capacity ◽

Power Demand ◽

Spent Fuel ◽

Fuel Management ◽

Fuel Characteristics ◽

Reactor Types ◽

Fuel Accumulation ◽

Reactor Pool

Nuclear power has satisfied the national electric power demand for three decades, and there are only two reactor types in Korea. The nuclear fuel species, however, have a large variety of fuel types, dimensions, initial enrichment, and fuel supply vendors. A spent fuel accumulation problem has arisen like any other country that uses nuclear power. The spent fuel wet storage capacity in the reactor pool is getting close to its limit, and so hence, short & long-term solutions are being actively proposed. First the general status for the nuclear industries and spent fuels will be introduced, then spent fuel characteristics will follow, and last the future anticipation of spent fuel management will close this article.

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Modelling of RBMK Spent Nuclear Fuel Characteristics

Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory ◽

10.1115/icone22-31005 ◽

2014 ◽

Author(s):

Arturas Smaizys ◽

Povilas Poskas ◽

Ernestas Narkunas

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

Fission Products ◽

Experimental Investigations ◽

Spent Fuel ◽

Radionuclide Content ◽

Fuel Assemblies ◽

Fuel Characteristics ◽

Final Shutdown ◽

Rbmk Fuel

After the final shutdown of Ignalina NPP, total amount of spent nuclear fuel is approximately 22 thousands of fuel assemblies. Radionuclide content and its characteristics in spent fuel are initial data for analysis of various safety related areas such as shielding, thermal analysis, radioactive releases and other processes. Experimental investigations of radionuclide content and characteristics in spent nuclear fuel are complicated and expensive, therefore numerical evaluation methods are widely used. Numerical modelling of spent RBMK fuel characteristics was performed using TRITON code from SCALE 6.1 system. Activities of fission products and actinides, gamma and neutron sources, decay heat obtained with TRITON code are compared with previous modelling results obtained using SAS2H sequence from the former SCALE 4.3 version. Some evaluated parameters are compared with published experimental data for RBMK spent nuclear fuel.

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