| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments
|
Haste, T.
|
|
2015
|
283 |
C |
p. 8-20
13 p.
|
artikel
|
| 2 |
Analysis of PWR ex-vessel steam explosion for axial and side melt release
|
Leskovar, Matjaž
|
|
2015
|
283 |
C |
p. 40-50
11 p.
|
artikel
|
| 3 |
Base irradiation simulation and its effect on fuel behavior prediction by TRANSURANUS code: Application to reactivity initiated accident condition
|
Lisovyy, Oleksandr
|
|
2015
|
283 |
C |
p. 162-167
6 p.
|
artikel
|
| 4 |
Cohesive zone modeling of intergranular cracking in polycrystalline aggregates
|
Simonovski, Igor
|
|
2015
|
283 |
C |
p. 139-147
9 p.
|
artikel
|
| 5 |
Critical power prediction by CATHARE2 of the OECD/NRC BFBT benchmark
|
Lutsanych, Sergii
|
|
2015
|
283 |
C |
p. 71-80
10 p.
|
artikel
|
| 6 |
Dose rates modeling of pressurized water reactor primary loop components with SCALE6.0
|
Matijević, Mario
|
|
2015
|
283 |
C |
p. 175-192
18 p.
|
artikel
|
| 7 |
Experimental investigation on powder conductivity for the application to double wall heat exchanger (NACIE-UP)
|
Rozzia, Davide
|
|
2015
|
283 |
C |
p. 100-113
14 p.
|
artikel
|
| 8 |
Impact of component unavailability uncertainty on safety systems unavailability
|
Volkanovski, Andrija
|
|
2015
|
283 |
C |
p. 193-201
9 p.
|
artikel
|
| 9 |
Mechanical properties of the steel T91 in contact with lead
|
Klecka, Jakub
|
|
2015
|
283 |
C |
p. 131-138
8 p.
|
artikel
|
| 10 |
Melting temperature of MOX fuel for FBR applications: TRANSURANUS modelling and experimental findings
|
Calabrese, R.
|
|
2015
|
283 |
C |
p. 148-154
7 p.
|
artikel
|
| 11 |
Microstructure and mechanical properties of Zircaloy-4 cladding hydrogenated at temperatures typical for loss-of-coolant accident (LOCA) conditions
|
Pshenichnikov, Anton
|
|
2015
|
283 |
C |
p. 33-39
7 p.
|
artikel
|
| 12 |
Post-test calculation of the QUENCH-17 bundle experiment with debris formation and bottom water reflood using thermal hydraulic and severe fuel damage code SOCRAT/V3
|
Vasiliev, A.
|
|
2015
|
283 |
C |
p. 21-32
12 p.
|
artikel
|
| 13 |
Preface
|
Cizelj, Leon
|
|
2015
|
283 |
C |
p. 1-
1 p.
|
artikel
|
| 14 |
Simulation of a SBLOCA in a hot leg. Scaling considerations and application to a nuclear power plant
|
Querol, A.
|
|
2015
|
283 |
C |
p. 81-99
19 p.
|
artikel
|
| 15 |
Simulation of hydrogen deflagration experiment – Benchmark exercise with lumped-parameter codes
|
Kljenak, Ivo
|
|
2015
|
283 |
C |
p. 51-59
9 p.
|
artikel
|
| 16 |
Simulations of flashing experiments in TOPFLOW facility with TRACE code
|
Mikuž, Blaž
|
|
2015
|
283 |
C |
p. 60-70
11 p.
|
artikel
|
| 17 |
Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1–4
|
Jäckel, Bernd S.
|
|
2015
|
283 |
C |
p. 2-7
6 p.
|
artikel
|
| 18 |
Stress assessment in piping under synthetic thermal loads emulating turbulent fluid mixing
|
Costa Garrido, Oriol
|
|
2015
|
283 |
C |
p. 114-130
17 p.
|
artikel
|
| 19 |
Uncertainty analysis of infinite homogeneous lead and sodium cooled fast reactors at beginning of life
|
Vanhanen, R.
|
|
2015
|
283 |
C |
p. 168-174
7 p.
|
artikel
|
| 20 |
Using TRIGA Mark II research reactor for irradiation with thermal neutrons
|
Kolšek, Aljaž
|
|
2015
|
283 |
C |
p. 155-161
7 p.
|
artikel
|
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