scholarly journals Historical survey of nuclear fuel utilization in U.S. LWR power plants. Final report

1979 ◽  
Author(s):  
S.E. Turner ◽  
W.J. Elgin ◽  
R.P. Hancock
Keyword(s):  
Nuclear Fuel ◽  
Power Plants ◽  
Final Report ◽  
Historical Survey ◽  
Fuel Utilization

Small nuclear power plants for power supply to the arctic regions: spent nuclear fuel radioactivity assessment

2018 ◽  
Vol 2018 (1) ◽  
pp. 75-86
Author(s):  
Vadim Alekseevich Naumov ◽  
Sergey Andreevich Gusak ◽  
Andrey Vadimovich Naumov
Keyword(s):  
Nuclear Fuel ◽  
Power Supply ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Spent Nuclear Fuel ◽  
The Arctic ◽  
Arctic Regions

A Literature Review: Smart Grids Impacts on Nuclear Power Plants Task 4: Project Final Report

2016 ◽  
Author(s):  
Michael Villaran ◽  
◽  
Meng Yue ◽  
Robert Lofaro ◽  
Athi Varuttamaseni ◽  
...  
Keyword(s):  
Literature Review ◽  
Smart Grids ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Final Report

scholarly journals Final Report, Project: Advanced Oxy-Combustion Technology Development and Scale Up for New and Existing Coal-Fired Power Plants (Phase II)

2019 ◽  
Author(s):  
Mark Fitzsimmons ◽  
Doug M. Heim ◽  
William Follett ◽  
Stevan Jovanovic ◽  
Makini Byron ◽  
...  
Keyword(s):  
Phase Ii ◽  
Power Plants ◽  
Technology Development ◽  
Scale Up ◽  
Final Report ◽  
Combustion Technology

scholarly journals Gap Analysis to Guide DOE R&D in Supporting Extended Storage and Transportation of Spent Nuclear Fuel: An FY2019 Assessment (Final Report)

2019 ◽  
Author(s):  
Melissa Christine Teague ◽  
Sylvia J. Saltzstein ◽  
Brady Hanson ◽  
Ken B. Sorenson ◽  
Geoffrey A. Freeze
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Gap Analysis ◽  
Final Report

scholarly journals Defining document for a design/operation evaluation model for BWR power plants. Final report

1977 ◽  
Author(s):  
J. P. McDonald ◽  
L. M. Smith
Keyword(s):  
Power Plants ◽  
Evaluation Model ◽  
Final Report

scholarly journals Location of condenser leaks at steam power plants. Technical planning study 78-775. Final report

1978 ◽  
Author(s):  
C. A. Pelletier ◽  
E. D. Barefoot ◽  
J. E. Cline
Keyword(s):  
Power Plants ◽  
Final Report ◽  
Planning Study ◽  
Steam Power ◽  
Steam Power Plants ◽  
Technical Planning

scholarly journals Small nuclear power plants for power supply in arctic regions: assessment of spent nuclear fuel radioactivity

2018 ◽  
Vol 4 (2) ◽  
pp. 119-125
Author(s):  
Vadim Naumov ◽  
Sergey Gusak ◽  
Andrey Naumov
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Fuel Cycle ◽  
Mass Composition ◽  
Published Data ◽  
Pressurized Water ◽  
Fuel Cycles ◽  
Reactor Cores

The purpose of the present study is the investigation of mass composition of long-lived radionuclides accumulated in the fuel cycle of small nuclear power plants (SNPP) as well as long-lived radioactivity of spent fuel of such reactors. Analysis was performed of the published data on the projects of SNPP with pressurized water-cooled reactors (LWR) and reactors cooled with Pb-Bi eutectics (SVBR). Information was obtained on the parameters of fuel cycle, design and materials of reactor cores, thermodynamic characteristics of coolants of the primary cooling circuit for reactor facilities of different types. Mathematical models of fuel cycles of the cores of reactors of ABV, KLT-40S, RITM-200M, UNITERM, SVBR-10 and SVBR-100 types were developed. The KRATER software was applied for mathematical modeling of the fuel cycles where spatial-energy distribution of neutron flux density is determined within multi-group diffusion approximation and heterogeneity of reactor cores is taken into account using albedo method within the reactor cell model. Calculation studies of kinetics of burnup of isotopes in the initial fuel load (235U, 238U) and accumulation of long-lived fission products (85Kr, 90Sr, 137Cs, 151Sm) and actinoids (238,239,240,241,242Pu, 236U, 237Np, 241Am, 244Cm) in the cores of the examined SNPP reactor facilities were performed. The obtained information allowed estimating radiation characteristics of irradiated nuclear fuel and implementing comparison of long-lived radioactivity of spent reactor fuel of the SNPPs under study and of their prototypes (nuclear propulsion reactors). The comparison performed allowed formulating the conclusion on the possibility in principle (from the viewpoint of radiation safety) of application of SNF handling technology used in prototype reactors in the transportation and technological process layouts of handling SNF of SNPP reactors.

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