nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
An innovative fast reactor core design for rapid reduction of separated Pu and its proliferation concerns
|
Fujioka, Rie |
|
2019 |
125 |
C |
p. 148-156 |
artikel |
2 |
A performance analysis of vertical steam generator using an entropy generation method
|
Bahmanyar, M.E. |
|
2019 |
125 |
C |
p. 212-221 |
artikel |
3 |
Applying the Serpent-DYN3D code sequence for the decay heat analysis of metallic fuel sodium fast reactor
|
Pereira, G. |
|
2019 |
125 |
C |
p. 291-306 |
artikel |
4 |
A single-step framework to generate spatially self-shielded multi-group cross sections from Monte Carlo transport simulations
|
Boyd, William |
|
2019 |
125 |
C |
p. 261-271 |
artikel |
5 |
A two-dimensional modal method for spatial rehomogenization of nodal cross sections and discontinuity-factor correction
|
Gamarino, Matteo |
|
2019 |
125 |
C |
p. 157-185 |
artikel |
6 |
Count-loss effect in determination of prompt neutron decay constant by neutron correlation methods that employ two sets of neutron counting systems
|
Kitamura, Yasunori |
|
2019 |
125 |
C |
p. 328-341 |
artikel |
7 |
Editorial Board
|
|
|
2019 |
125 |
C |
p. ii |
artikel |
8 |
Establishment and application of cross-comparison model on redundancy differential pressure type flow channels
|
Chen, Yongwei |
|
2019 |
125 |
C |
p. 132-137 |
artikel |
9 |
Evaluation of activated corrosion products in primary coolant circuit of AP-1000 under grid frequency stability mode
|
Mahmood, Fiaz |
|
2019 |
125 |
C |
p. 138-147 |
artikel |
10 |
Experimental study on performance of helium high pressure compressors of HTR-10GT
|
Ming, Liang |
|
2019 |
125 |
C |
p. 318-327 |
artikel |
11 |
Game theory based complex analysis for nuclear security using non-zero sum algorithm
|
Woo, Tae Ho |
|
2019 |
125 |
C |
p. 12-17 |
artikel |
12 |
Investigations of accelerator reliability and decay heat removal for accelerator-driven system
|
Sugawara, Takanori |
|
2019 |
125 |
C |
p. 242-248 |
artikel |
13 |
Irradiation testing of enhanced uranium oxide fuels
|
Insulander Björk, Klara |
|
2019 |
125 |
C |
p. 99-106 |
artikel |
14 |
Maximum efficiency nuclear waste transmutation
|
Wallenius, Janne |
|
2019 |
125 |
C |
p. 74-79 |
artikel |
15 |
Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core
|
Syrjälahti, Elina |
|
2019 |
125 |
C |
p. 121-131 |
artikel |
16 |
Modeling of the SPERT transients using Serpent 2 with time-dependent capabilities
|
Levinsky, Alex |
|
2019 |
125 |
C |
p. 80-98 |
artikel |
17 |
Multi-group effective cross section calculation method for Fully Ceramic Micro-encapsulated fuel
|
Yin, Wen |
|
2019 |
125 |
C |
p. 26-37 |
artikel |
18 |
Multiphysics reactor-core simulations using the improved quasi-static method
|
Prince, Zachary M. |
|
2019 |
125 |
C |
p. 186-200 |
artikel |
19 |
Neutronics performance analysis on neutron consumption in a Fusion-Fission Hybrid System for tritium breeding
|
Hong, Seong Hee |
|
2019 |
125 |
C |
p. 201-211 |
artikel |
20 |
Nth-order multi-response CADIS method to optimize regional variances in a hybrid Monte Carlo simulation
|
Kim, Do Hyun |
|
2019 |
125 |
C |
p. 307-317 |
artikel |
21 |
On the over-conservatism of the 5% depletion uncertainty rule in spent fuel criticality analyses
|
Metwally, Walid A. |
|
2019 |
125 |
C |
p. 1-11 |
artikel |
22 |
On the solution of the neutron diffusion kinetic equation in planar geometry free of stiffness with convergence analysis
|
Tumelero, Fernanda |
|
2019 |
125 |
C |
p. 272-282 |
artikel |
23 |
Scaling analysis of melt jets and solidification modes
|
Iwasawa, Yuzuru |
|
2019 |
125 |
C |
p. 231-241 |
artikel |
24 |
Sensitivity analysis and similarity evaluation of sodium-cooled fast reactor in large size
|
Zheng, Youqi |
|
2019 |
125 |
C |
p. 283-290 |
artikel |
25 |
Sensitivity study of forced convection bubbling in a transparent viscous fluid as a proxy for molten borosilicate glass
|
Guillen, Donna Post |
|
2019 |
125 |
C |
p. 38-49 |
artikel |
26 |
Specific heat capacity model for compacted bentonite buffer materials
|
Yoon, Seok |
|
2019 |
125 |
C |
p. 18-25 |
artikel |
27 |
Studies on sodium aerosols dispersion in open environment for fast reactor safety
|
Subramanian, V. |
|
2019 |
125 |
C |
p. 63-73 |
artikel |
28 |
The impact of emergency operating safety procedures on mitigation the nuclear thermal power plant severe accident
|
Sayed Ahmed, Sami I.A. |
|
2019 |
125 |
C |
p. 222-230 |
artikel |
29 |
Transient analysis of C5G7-TD benchmark with MPACT
|
Shen, Qicang |
|
2019 |
125 |
C |
p. 107-120 |
artikel |
30 |
Validation and evaluation of the ADVANTG code on the ICSBEP skyshine benchmark experiment
|
Kotnik, Domen |
|
2019 |
125 |
C |
p. 249-260 |
artikel |
31 |
Validation of statistical uncertainties in subcritical benchmark measurements: Part II – Measured data
|
Hutchinson, Jesson |
|
2019 |
125 |
C |
p. 342-359 |
artikel |
32 |
Validation of statistical uncertainties in subcritical benchmark measurements: Part I – Theory and simulations
|
Hutchinson, Jesson |
|
2019 |
125 |
C |
p. 50-62 |
artikel |