| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A method for calculating the assembly bowing reactivity coefficients in sodium fast reactor
|
Wang, Yongping
|
|
|
155 |
C |
p.
|
artikel
|
| 2 |
Analysis of the two-step source term calculation method with the high-fidelity source term calculation capability
|
Liu, Zhouyu
|
|
|
155 |
C |
p.
|
artikel
|
| 3 |
Comparison of spallation and fusion neutron sources in fuel transmutation and regeneration
|
Barros, Graiciany
|
|
|
155 |
C |
p.
|
artikel
|
| 4 |
Contribution to the verification of the MORET 5 code using the CROCUS reactor physics benchmark
|
Leclaire, N.
|
|
|
155 |
C |
p.
|
artikel
|
| 5 |
CORE SIM+: A flexible diffusion-based solver for neutron noise simulations
|
Mylonakis, Antonios
|
|
|
155 |
C |
p.
|
artikel
|
| 6 |
Demand characteristics of component parts of Korean nuclear power plants depending on reactor type at the operation stage
|
Park, Sung-Ho
|
|
|
155 |
C |
p.
|
artikel
|
| 7 |
Development and verification of the coupled thermal–hydraulic code – TRACE/SCF based on the ICoCo interface and the SALOME platform
|
Zhang, Kanglong
|
|
|
155 |
C |
p.
|
artikel
|
| 8 |
Development of a correlation for mixed convection heat transfer in rod bundles
|
Li, Junlong
|
|
|
155 |
C |
p.
|
artikel
|
| 9 |
Does neutron clustering affect tally errors in Monte Carlo criticality calculations?
|
Mickus, Ignas
|
|
|
155 |
C |
p.
|
artikel
|
| 10 |
3D SN and Monte Carlo calculations of the Utah TRIGA reactor core using PENTRAN and MCNP6
|
Wang, Meng-Jen
|
|
|
155 |
C |
p.
|
artikel
|
| 11 |
Dynamic response of dry cask storage systems for spent nuclear fuel to near field blast loading
|
Hanifehzadeh, Mohammad
|
|
|
155 |
C |
p.
|
artikel
|
| 12 |
Editorial Board
|
|
|
|
155 |
C |
p.
|
artikel
|
| 13 |
Experimental investigation on instability characteristics of loss of heat sink accident in a natural circulation system
|
Lin, Yuqi
|
|
|
155 |
C |
p.
|
artikel
|
| 14 |
Fission gas release from irradiated mixed-oxide fuel pellet during simulated reactivity-initiated accident conditions: Results of BZ-3 and BZ-4 tests
|
Kakiuchi, Kazuo
|
|
|
155 |
C |
p.
|
artikel
|
| 15 |
Full-core reactor physics analysis for accident tolerant cladding in a VVER-1000 reactor
|
Safarzadeh, O.
|
|
|
155 |
C |
p.
|
artikel
|
| 16 |
Hybrid depletion framework using mixed-fidelity transport solutions and substeps
|
Johnson, Andrew
|
|
|
155 |
C |
p.
|
artikel
|
| 17 |
Hybrid finite-element-based numerical solution of the multi-group SP3 equations and its application on hexagonal reactor problems
|
Babcsány, Boglárka
|
|
|
155 |
C |
p.
|
artikel
|
| 18 |
Longitudinal deformation study of pressure tube of Indian PHWR under high temperature transient
|
Singh, Ankit R.
|
|
|
155 |
C |
p.
|
artikel
|
| 19 |
Mathematical and numerical investigation of Ledinegg flow excursion and dynamic instability of natural circulation loop at supercritical condition
|
Kumar Rai, Santosh
|
|
|
155 |
C |
p.
|
artikel
|
| 20 |
Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR
|
Al-Zahrani, Yahya A.
|
|
|
155 |
C |
p.
|
artikel
|
| 21 |
Non-intrusive stochastic approach for nuclear cross-sections adjustment
|
Huang, Dongli
|
|
|
155 |
C |
p.
|
artikel
|
| 22 |
Numerical analysis of liquid fall type gas entrainment in pool-type fast reactor
|
Yao, Hao
|
|
|
155 |
C |
p.
|
artikel
|
| 23 |
On the Feynman-alpha method for reflected fissile assemblies
|
Hua, Michael Y.
|
|
|
155 |
C |
p.
|
artikel
|
| 24 |
Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part I: Methodology demonstration
|
Di Nora, V.A.
|
|
|
155 |
C |
p.
|
artikel
|
| 25 |
Optimization study of pressurized water reactor secondary neutron source location
|
Ding, Qianxue
|
|
|
155 |
C |
p.
|
artikel
|
| 26 |
Photoneutron production in heavy water reactor fuel lattice from accelerator-driven bremsstrahlung
|
Fynan, Douglas A.
|
|
|
155 |
C |
p.
|
artikel
|
| 27 |
Rotor dynamic analysis of the vertical hydro-hybrid bearing rotor coupled system of a two-circuit main loop liquid Sodium pump system
|
Xie, Zhongliang
|
|
|
155 |
C |
p.
|
artikel
|
| 28 |
Spectral analysis of the extended linear discontinuous method for one-dimensional monoenergetic discrete ordinates transport problems in non-multiplying media
|
Ortiz, Iram B.R.
|
|
|
155 |
C |
p.
|
artikel
|
| 29 |
Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor
|
Ványi, A.Sz.
|
|
|
155 |
C |
p.
|
artikel
|
| 30 |
Study of CAP1400 secondary pipe wall thinning rate under flow accelerated corrosion
|
Rao, Delin
|
|
|
155 |
C |
p.
|
artikel
|
| 31 |
The development of a novel adaptive genetic algorithm for the optimization of fuel cycle length
|
Kubiński, Wojciech
|
|
|
155 |
C |
p.
|
artikel
|
Tijdschrift beschrijving