2755-967x

Nuclear Science and Technology Open Research

F1000 Research Ltd

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1

Attach ORCID iDs across 5 articles

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DOIs for this ISSN

Showing the top 5 of 86 DOIs, ordered by correction priority.

# Title Missing Priority Citations
1 Numerical simulation of thermo-throttle for iodine flow rate… (10.12688/nuclscitechnolopenres.17411.1)
ORCID
11.93 2
2 Steam Condensation Scaled Experiment in the Presence of Non-… (10.12688/nuclscitechnolopenres.17625.1)
ORCID
11.93 2
3 A theory and analysis of the impact of gas in the dynamical… (10.12688/nuclscitechnolopenres.17428.1)
0.00 1
4 Neutronic analysis of the BYU molten salt micro reactor (10.12688/nuclscitechnolopenres.17435.1)
0.00 2
5 Shielding factors for a fission-powered mars exploration rov… (10.12688/nuclscitechnolopenres.17438.1)
0.00 1
6 Shielding factors for a fission-powered mars exploration rov… (10.12688/nuclscitechnolopenres.17438.2)
0.00 0
7 Shielding factors for a fission-powered mars exploration rov… (10.12688/nuclscitechnolopenres.17438.3)
0.00 0
8 Shielding factors for a fission-powered mars exploration rov… (10.12688/nuclscitechnolopenres.17438.4)
0.00 0
9 Design of an optimized nuclear fuel pellet (10.12688/nuclscitechnolopenres.17443.1)
0.00 1
10 Reexamination of a 40Ca(n,α)37Ar cross section measurement f… (10.12688/nuclscitechnolopenres.17446.1)
0.00 1
11 Reexamination of a 40Ca(n,α)37Ar cross section measurement f… (10.12688/nuclscitechnolopenres.17446.2)
0.00 1
12 Shutdown dose rate calculations in high-temperature gas-cool… (10.12688/nuclscitechnolopenres.17447.1)
0.00 0
13 Shutdown dose rate calculations in high-temperature gas-cool… (10.12688/nuclscitechnolopenres.17447.2)
0.00 1
14 Optimal sizing toolbox for energy generation and storage for… (10.12688/nuclscitechnolopenres.17453.1)
0.00 0
15 Covert system for detecting nuclear dirty bombs in public ve… (10.12688/nuclscitechnolopenres.17455.1)
0.00 0
16 Nanocomposite physics and structure considerations in MCNP p… (10.12688/nuclscitechnolopenres.17456.1)
0.00 1
17 Fabrication and metrology of SiC cladding and seals for cont… (10.12688/nuclscitechnolopenres.17457.1)
0.00 0
18 Fabrication and metrology of SiC cladding and seals for cont… (10.12688/nuclscitechnolopenres.17457.2)
0.00 0
19 Molten Salt Reactor Loss of Flow Accident Analysis using the… (10.12688/nuclscitechnolopenres.17459.1)
0.00 2
20 Molten Salt Reactor Loss of Flow Accident Analysis using the… (10.12688/nuclscitechnolopenres.17459.2)
0.00 1
21 Development and evaluation of parallel simulated annealing a… (10.12688/nuclscitechnolopenres.17464.1)
0.00 0
22 Development and evaluation of parallel simulated annealing a… (10.12688/nuclscitechnolopenres.17464.2)
0.00 1
23 A more open future for nuclear science and technology (10.12688/nuclscitechnolopenres.17478.1)
0.00 0
24 The Bimodal Epithermal Astronuclear Reactor (BEAR): A LONG-L… (10.12688/nuclscitechnolopenres.17481.1)
0.00 0
25 The Bimodal Epithermal Astronuclear Reactor (BEAR): A Long-L… (10.12688/nuclscitechnolopenres.17481.2)
0.00 0
26 Decision-making based on Markov decision process in integrat… (10.12688/nuclscitechnolopenres.17490.1)
0.00 2
27 Decision-making based on Markov decision process in integrat… (10.12688/nuclscitechnolopenres.17491.1)
0.00 0
28 CFD model for predicting spent nuclear fuel drying condition… (10.12688/nuclscitechnolopenres.17492.1)
0.00 1
29 CFD model for predicting spent nuclear fuel drying condition… (10.12688/nuclscitechnolopenres.17492.2)
0.00 0
30 CFD model for predicting spent nuclear fuel drying condition… (10.12688/nuclscitechnolopenres.17492.3)
0.00 0
31 A general-purpose code for correlated sampling using batch s… (10.12688/nuclscitechnolopenres.17496.1)
0.00 0
32 Radiator production for Pylon Fission Surface Power System t… (10.12688/nuclscitechnolopenres.17501.1)
0.00 0
33 Progress on Pu-238 production at Idaho National Laboratory f… (10.12688/nuclscitechnolopenres.17503.1)
0.00 0
34 Deployment of small modular reactors in the European Union (10.12688/nuclscitechnolopenres.17510.1)
0.00 4
35 Deployment of small modular reactors in the European Union (10.12688/nuclscitechnolopenres.17510.2)
0.00 0
36 Deployment of small modular reactors in the European Union (10.12688/nuclscitechnolopenres.17510.3)
0.00 0
37 Tensile and creep properties of small specimens of reduced-a… (10.12688/nuclscitechnolopenres.17514.1)
0.00 0
38 Risk-Informed Performance-Based methods for cyber-attack on… (10.12688/nuclscitechnolopenres.17523.1)
0.00 0
39 A literature review of pyroprocessing safeguards (10.12688/nuclscitechnolopenres.17524.1)
0.00 4
40 Proliferation Analysis of Multiple Recycling of Re-enriched… (10.12688/nuclscitechnolopenres.17535.1)
0.00 0
41 Proliferation Analysis of Multiple Recycling of Re-enriched… (10.12688/nuclscitechnolopenres.17535.2)
0.00 0
42 A new approach to monitoring solvent extraction processes fo… (10.12688/nuclscitechnolopenres.17540.1)
0.00 1
43 Enhanced material identification via momentum-integrated muo… (10.12688/nuclscitechnolopenres.17545.1)
0.00 0
44 Concept design, application and optimization of operational… (10.12688/nuclscitechnolopenres.17546.1)
0.00 0
45 Concept design, application and optimization of operational… (10.12688/nuclscitechnolopenres.17546.2)
0.00 0
46 Influence of neutron decay on nuclear reactor materials (10.12688/nuclscitechnolopenres.17547.1)
0.00 0
47 Developing A Digital Twin of a TRUEX Extraction Process that… (10.12688/nuclscitechnolopenres.17549.1)
0.00 4
48 Challenges and Considerations in Transitioning from Cobalt-6… (10.12688/nuclscitechnolopenres.17558.1)
0.00 0
49 Detection of Axial Locations of Control Rods Using Movable I… (10.12688/nuclscitechnolopenres.17561.1)
0.00 0
50 Detection of Axial Locations of Control Rods Using Movable I… (10.12688/nuclscitechnolopenres.17561.2)
0.00 0