Nome |
# |
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c0d-8364-4599-e053-1705fe0aef77
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816
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Properties of the high burnup structure in nuclear light water reactor fuel, file e0c31c0c-258e-4599-e053-1705fe0aef77
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471
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Final report on rod cladding failure during SGTR, file eedd6d35-ee8e-41eb-a9f7-a64f0d904d50
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149
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SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes, file e0c31c0f-4faa-4599-e053-1705fe0aef77
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146
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A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools, file e0c31c0c-1c20-4599-e053-1705fe0aef77
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134
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Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, file e0c31c0f-3db2-4599-e053-1705fe0aef77
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123
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Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation, file e0c31c0f-aa25-4599-e053-1705fe0aef77
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122
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A Continuum Dislocation Dynamics Crystal Plasticity Approach to Irradiated BCC α-Iron, file e0c31c11-c717-4599-e053-1705fe0aef77
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120
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Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations, file e0c31c0b-9f7d-4599-e053-1705fe0aef77
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119
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Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant, file e0c31c0c-8282-4599-e053-1705fe0aef77
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109
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Microhardness and Young's modulus of high burn-up UO2 fuel, file e0c31c09-bec0-4599-e053-1705fe0aef77
|
103
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Spaceship Earth. Space-driven technologies and systems for sustainability on ground, file e0c31c08-6086-4599-e053-1705fe0aef77
|
95
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Development of best estimate numerical tools for LFR design and safety analysis, file e0c31c11-2334-4599-e053-1705fe0aef77
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85
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Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions, file e0c31c12-7f7d-4599-e053-1705fe0aef77
|
84
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Incorporation and verification of models and properties in fuel performance codes, file e0c31c11-3282-4599-e053-1705fe0aef77
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74
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Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients, file e0c31c10-072f-4599-e053-1705fe0aef77
|
72
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IAEA FUMAC BENCHMARK ON THE HALDEN, STUDISVIK AND QUENCH-L1 LOCA TESTS, file e0c31c0d-3713-4599-e053-1705fe0aef77
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65
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Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes, file e0c31c10-d8a9-4599-e053-1705fe0aef77
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63
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Report describing the irradiation experiments selected for the assessment of fuel performance codes, file e0c31c11-43a5-4599-e053-1705fe0aef77
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60
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Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e0c31c11-66e1-4599-e053-1705fe0aef77
|
57
|
Review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour, file e0c31c10-f6f8-4599-e053-1705fe0aef77
|
56
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SCIANTIX: A new meso-scale module enhancing fuel performance simulations, file e0c31c0f-08d5-4599-e053-1705fe0aef77
|
53
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Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications, file e0c31c0f-a502-4599-e053-1705fe0aef77
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53
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3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms, file e0c31c11-c716-4599-e053-1705fe0aef77
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48
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A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors, file e0c31c11-730b-4599-e053-1705fe0aef77
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46
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Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX, file 349fe6f6-fa64-44f8-aec3-7a8681055a88
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38
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Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS, file d13d261f-9f9a-4562-8111-6b2968efa829
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38
|
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions, file 4a4c0296-13dc-4e2c-b862-41e38364b1b6
|
34
|
Synthesis of INSPYRE results, file d48a7793-5d73-4d02-95c2-ff437496291b
|
30
|
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, file e7e10bd5-806d-4a25-bb59-2875e7d449d7
|
30
|
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution, file e0c31c12-87ff-4599-e053-1705fe0aef77
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27
|
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation, file e0c31c12-e999-4599-e053-1705fe0aef77
|
27
|
Synthesis of the presentation of INSPYRE results to the User Group, file 9a0544ca-5818-490a-85d3-5a4c8b737046
|
26
|
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study, file e0c31c11-5faa-4599-e053-1705fe0aef77
|
26
|
Synthesis of the inert gas behaviour models developed in INSPYRE, file e0c31c11-000c-4599-e053-1705fe0aef77
|
24
|
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor, file e0c31c11-f94e-4599-e053-1705fe0aef77
|
24
|
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data, file e0c31c11-831e-4599-e053-1705fe0aef77
|
21
|
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study, file 67e60494-3ef6-499b-8963-3f77d2331374
|
20
|
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes, file e0c31c12-890d-4599-e053-1705fe0aef77
|
18
|
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX, file 51c36818-c26d-4300-b58e-37b5bc8c7a52
|
16
|
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error, file e0c31c12-4a03-4599-e053-1705fe0aef77
|
16
|
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases, file fbc03e51-510d-4843-8083-35c8f07eddb4
|
14
|
Synthesis of the First User Group Meeting, file e0c31c11-000a-4599-e053-1705fe0aef77
|
13
|
Description of new meso-scale models and their implementation in fuel performance codes, file f6e82746-a87a-47b7-83bf-d9526b4bc972
|
11
|
Third Yearly Activity Report, file 0c5e3fa9-5fbd-42e1-9cb8-2743db035309
|
9
|
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions, file e0c31c0f-0a02-4599-e053-1705fe0aef77
|
9
|
Towards multi-physics description of fuel behaviour for accidental conditions, file 0c5511c1-ac74-4094-926f-0b879e7fbf96
|
5
|
A surrogate model for the helium production rate in fast reactor MOX fuels, file 1888f666-30df-4998-9078-06f8d76bfe67
|
4
|
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution, file 24714dd1-5353-40ed-89b1-d8ad52be28bc
|
4
|
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F, file a6d0aca8-8468-4fbb-bb76-009d1762af4e
|
4
|
Best practices and QA protocols for code development, file c4e790d9-b3ed-40f8-999d-9fa78dd49637
|
4
|
Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor, file e0c31c08-1def-4599-e053-1705fe0aef77
|
4
|
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS, file e0c31c0a-3b50-4599-e053-1705fe0aef77
|
4
|
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions, file 7fae6c01-455c-469a-9376-53438664a5ba
|
3
|
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments, file c23885ec-ea54-4582-8235-430650f27c8b
|
3
|
A reduced order model for fission gas diffusion in columnar grains, file c302733e-ec86-4a6f-b53d-00bf256fb749
|
3
|
Spaceship Earth. Space-driven technologies and systems for sustainability on ground, file e0c31c08-5d85-4599-e053-1705fe0aef77
|
3
|
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions, file e0c31c0a-dfdd-4599-e053-1705fe0aef77
|
3
|
Modelling of Transient Fission Gas Behaviour in Oxide Fuel and Application to the BISON Code, file e0c31c07-be9f-4599-e053-1705fe0aef77
|
2
|
Spaceship Earth. Space-Driven Technologies and Systems for Sustainability on Ground, file e0c31c08-254c-4599-e053-1705fe0aef77
|
2
|
A semi-empirical model for the formation and depletion of the high burnup structure in UO2, file e0c31c0a-4990-4599-e053-1705fe0aef77
|
2
|
Advancement in FGR modeling for transient analysis of FR fuel, file e0c31c0b-6baa-4599-e053-1705fe0aef77
|
2
|
Modelling Fission Gas Behaviour with the BISON Fuel Performance Code, file e0c31c0c-054d-4599-e053-1705fe0aef77
|
2
|
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution, file e0c31c0c-8549-4599-e053-1705fe0aef77
|
2
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Isotropic softening model for fuel cracking in BISON, file e0c31c0c-d421-4599-e053-1705fe0aef77
|
2
|
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel, file e0c31c10-96ba-4599-e053-1705fe0aef77
|
2
|
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON, file e0c31c10-e626-4599-e053-1705fe0aef77
|
2
|
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior, file e0c31c11-9d75-4599-e053-1705fe0aef77
|
2
|
Greenspace: Towards a Systematic, Global and Innovative Evaluation of the Environmental Impact of Space Activities for a Safe and Sustainable Space Environment, file e0c31c08-254b-4599-e053-1705fe0aef77
|
1
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Modelling of Burst Release in Oxide Fuel and Application to the Transuranus Code, file e0c31c0a-6bbb-4599-e053-1705fe0aef77
|
1
|
Modeling Fission Gas Release and Bubble Evolution in UO2 for Engineering Fuel Rod Analysis, file e0c31c0c-de4b-4599-e053-1705fe0aef77
|
1
|
Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis, file e0c31c0d-38d9-4599-e053-1705fe0aef77
|
1
|
Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor, file f6def39d-fa91-41ac-90db-a0f8164f4e59
|
1
|
Totale |
3.863 |