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1992, AECL research, ISBN 0660147858, Volume 10685, 16
Book
Annals of Nuclear Energy, ISSN 0306-4549, 08/2015, Volume 82, pp. 142 - 150
The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical Research Centre of Finland since 2004, and is currently... 
Reactor physics | Homogenization | Serpent | Burnup calculation | Monte Carlo | SYSTEM | CORE | PREDICTOR-CORRECTOR METHOD | BATEMAN SOLUTIONS | CRITICAL REACTORS | DYN3D | NUMERICAL STABILITY | BURNUP CALCULATIONS | NUCLEAR SCIENCE & TECHNOLOGY | FUEL | PHYSICS | Monte Carlo methods | Mathematical analysis | Organizations | Documents | Nuclear reactor components | Nuclear engineering | Nuclear reactors
Journal Article
Nuclear Engineering and Technology, ISSN 1738-5733, 09/2019, Volume 51, Issue 6, pp. 1708 - 1714
The purpose of the critical evaluation of the spent fuel pool (SFP) is to verify that the maximum effective multiplication factor (K ) is less than the... 
Spent fuel | Rack | Spent fuel pool | Axial burnup profile | Burnup credit | Neutron absorber | Uniform burnup profile | Criticality | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 05/2020, Volume 139, p. 107159
Molten salt reactors have seen a resurgence of interest in the last 20 years and yet the options available for fuel evolution modelling in these systems are... 
MSR molten salt dynamics burnup optimization
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 01/2020, Volume 135, p. 106969
This paper presents the neutronic and thermal-hydraulic analysis of a small CANDLE reactor with the melt-refining process. This process is applied to recycle... 
Burnup performance | Compensating for fuel losses | Small CANDLE reactor | Fuel cladding integrity | Melt-refining process | NUCLEAR SCIENCE & TECHNOLOGY | BURNUP
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 02/2018, Volume 52, Issue 2, pp. 204 - 209
Journal Article
He Jishu/Nuclear Techniques, ISSN 0253-3219, 11/2018, Volume 41, Issue 11
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 08/2015, Volume 83, Issue C, pp. 186 - 190
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 11/2016, Volume 50, Issue 11, pp. 2010 - 2017
Journal Article
Nuclear Engineering and Technology, ISSN 1738-5733, 09/2019
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 01/2018, Volume 52, Issue 1, pp. 101 - 106
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 07/2018, Volume 106, pp. 64 - 71
The operator associated with the neutron transport equation is not self-adjoint. The solution to the adjoint transport equation is orthogonal to the solution... 
Burnup dependent neutron importance | Burnup calculation | MCNIC method | VVER-1000 reactor | CODE SYSTEM | NUCLEAR SCIENCE & TECHNOLOGY | Nuclear reactors
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 05/2020, Volume 139, p. 107244
Monte Carlo burnup simulations continue to be seen as computationally very expensive numerical routines despite recent developments of associated methods.... 
Time step length | Monte Carlo burnup calculations | Efficiency | Optimisation | Statistics
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 04/2020, Volume 138, p. 107191
The axial variation of Pu quality ([Pu-239 + Pu-241]/Pu) in used nuclear fuel is analyzed using MCNP simulations. The Pu quality ratio variation is found to be... 
Plutonium quality ratio | Nuclear material attractiveness | Plutonium variation | Burnup | MCNP
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 03/2020, Volume 137, p. 107162
A liquid-fueled molten salt reactor (MSR) can be flexibly designed as a thermal, epithermal or fast system. Meanwhile, available online fuel reprocessing can... 
Radiotoxicity | Deep burnup | Minor actinides | Thorium based molten salt reactor
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 02/2020, Volume 136, p. 107006
The generation and transmutation process of the transplutoniums in the conversion chains for cf production is calculated and analyzed. The production and... 
Fast reactor | Transport-burnup | Neutron spectrum | Conversion efficiency | Coupling
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 06/2011, Volume 45, Issue 6, pp. 700 - 704
Journal Article
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