| no |
title |
author |
magazine |
year |
volume |
issue |
page(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
|
article
|
| 2 |
A performance analysis of vertical steam generator using an entropy generation method
|
Bahmanyar, M.E.
|
|
2019
|
125 |
C |
p. 212-221
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 7 |
Editorial Board
|
|
|
2019
|
125 |
C |
p. ii
|
article
|
| 8 |
Establishment and application of cross-comparison model on redundancy differential pressure type flow channels
|
Chen, Yongwei
|
|
2019
|
125 |
C |
p. 132-137
|
article
|
| 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
|
article
|
| 10 |
Experimental study on performance of helium high pressure compressors of HTR-10GT
|
Ming, Liang
|
|
2019
|
125 |
C |
p. 318-327
|
article
|
| 11 |
Game theory based complex analysis for nuclear security using non-zero sum algorithm
|
Woo, Tae Ho
|
|
2019
|
125 |
C |
p. 12-17
|
article
|
| 12 |
Investigations of accelerator reliability and decay heat removal for accelerator-driven system
|
Sugawara, Takanori
|
|
2019
|
125 |
C |
p. 242-248
|
article
|
| 13 |
Irradiation testing of enhanced uranium oxide fuels
|
Insulander Björk, Klara
|
|
2019
|
125 |
C |
p. 99-106
|
article
|
| 14 |
Maximum efficiency nuclear waste transmutation
|
Wallenius, Janne
|
|
2019
|
125 |
C |
p. 74-79
|
article
|
| 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
|
article
|
| 16 |
Modeling of the SPERT transients using Serpent 2 with time-dependent capabilities
|
Levinsky, Alex
|
|
2019
|
125 |
C |
p. 80-98
|
article
|
| 17 |
Multi-group effective cross section calculation method for Fully Ceramic Micro-encapsulated fuel
|
Yin, Wen
|
|
2019
|
125 |
C |
p. 26-37
|
article
|
| 18 |
Multiphysics reactor-core simulations using the improved quasi-static method
|
Prince, Zachary M.
|
|
2019
|
125 |
C |
p. 186-200
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 23 |
Scaling analysis of melt jets and solidification modes
|
Iwasawa, Yuzuru
|
|
2019
|
125 |
C |
p. 231-241
|
article
|
| 24 |
Sensitivity analysis and similarity evaluation of sodium-cooled fast reactor in large size
|
Zheng, Youqi
|
|
2019
|
125 |
C |
p. 283-290
|
article
|
| 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
|
article
|
| 26 |
Specific heat capacity model for compacted bentonite buffer materials
|
Yoon, Seok
|
|
2019
|
125 |
C |
p. 18-25
|
article
|
| 27 |
Studies on sodium aerosols dispersion in open environment for fast reactor safety
|
Subramanian, V.
|
|
2019
|
125 |
C |
p. 63-73
|
article
|
| 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
|
article
|
| 29 |
Transient analysis of C5G7-TD benchmark with MPACT
|
Shen, Qicang
|
|
2019
|
125 |
C |
p. 107-120
|
article
|
| 30 |
Validation and evaluation of the ADVANTG code on the ICSBEP skyshine benchmark experiment
|
Kotnik, Domen
|
|
2019
|
125 |
C |
p. 249-260
|
article
|
| 31 |
Validation of statistical uncertainties in subcritical benchmark measurements: Part II – Measured data
|
Hutchinson, Jesson
|
|
2019
|
125 |
C |
p. 342-359
|
article
|
| 32 |
Validation of statistical uncertainties in subcritical benchmark measurements: Part I – Theory and simulations
|
Hutchinson, Jesson
|
|
2019
|
125 |
C |
p. 50-62
|
article
|
Journal description