| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Activation energy determination and kinetic modeling of thorium oxide dissolution in nitric acid/ hydrofluoric acid system: Influence of fluoride ion on ThO2 dissolution
|
Keshtkar, Ali Reza
|
|
2016
|
93 |
C |
p. 362-370
9 p.
|
artikel
|
| 2 |
Active fast neutron singles assay of 235U enrichment in small samples of triuranium octoxide
|
Parker, Helen M.O.
|
|
2016
|
93 |
C |
p. 59-66
8 p.
|
artikel
|
| 3 |
An assessment of a VVER-1000 core during Turbo-Generator load reduction test using RELAP5/MOD3.2 and WIMSD-5B/PARCSv2.7
|
Vahman, Navid
|
|
2016
|
93 |
C |
p. 155-164
10 p.
|
artikel
|
| 4 |
An investigation on flashing instability induced water hammer in an open natural circulation system
|
Hou, Xiaofan
|
|
2016
|
93 |
C |
p. 418-430
13 p.
|
artikel
|
| 5 |
A novel multi objective Loading Pattern Optimization by Gravitational Search Algorithm (GSA) for WWER1000 core
|
Aghaie, M.
|
|
2016
|
93 |
C |
p. 1-11
11 p.
|
artikel
|
| 6 |
A use of prototypic material for the investigation of severe accident progression
|
Song, JinHo
|
|
2016
|
93 |
C |
p. 297-305
9 p.
|
artikel
|
| 7 |
Benchmark description of a stylized three-dimensional European Pressurized Reactor (EPR) problem
|
Lago, Daniel
|
|
2016
|
93 |
C |
p. 18-46
29 p.
|
artikel
|
| 8 |
Comparative analyses of coated and composite UN fuel – Monte Carlo based full core LWR study
|
Ahmed, Hassam
|
|
2016
|
93 |
C |
p. 260-266
7 p.
|
artikel
|
| 9 |
Comparative analysis of RIA and LOCA with and without fuel rod behavior modeling in THEATRe code
|
Nawaz, Amjad
|
|
2016
|
93 |
C |
p. 133-145
13 p.
|
artikel
|
| 10 |
Development of a thermal-hydraulic subchannel analysis code for motion conditions
|
Cai, Rong
|
|
2016
|
93 |
C |
p. 165-176
12 p.
|
artikel
|
| 11 |
Dismantling of the graphite pile of Latina NPP: Characterization and handling/removal equipment for single brick or multi-bricks
|
Canzone, Giuseppe
|
|
2016
|
93 |
C |
p. 146-154
9 p.
|
artikel
|
| 12 |
Dosimetry assessment during the sipping test in the IPR-R1 TRIGA reactor using MCNPX
|
Gual, Maritza R.
|
|
2016
|
93 |
C |
p. 238-245
8 p.
|
artikel
|
| 13 |
Dynamic thermal-hydraulic modelling of the EU DEMO HCPB breeding blanket cooling loops
|
Froio, A.
|
|
2016
|
93 |
C |
p. 116-132
17 p.
|
artikel
|
| 14 |
Editorial Board
|
|
|
2016
|
93 |
C |
p. IFC-
1 p.
|
artikel
|
| 15 |
Effect of heat treatment on neutron attenuation characteristics of high density concretes (HDC)
|
C., Sivathanu Pillai
|
|
2016
|
93 |
C |
p. 76-83
8 p.
|
artikel
|
| 16 |
Estimation of a boundary to distinguish between radioactive materials and non-radioactive materials around a Main Steam line and a Feed Water line in a Biological Shielding Wall of a BWR for decommissioning
|
Tanaka, Ken-ichi
|
|
2016
|
93 |
C |
p. 371-385
15 p.
|
artikel
|
| 17 |
Evaluation of the specific radioactivity of 40 elements created by nuclear transmutation of fission products
|
Terashima, Atsunori
|
|
2016
|
93 |
C |
p. 177-185
9 p.
|
artikel
|
| 18 |
Experimental and numerical investigation of natural circulation stability of the SHUNCL thermal-hydraulic loop
|
Rabiee, Ataollah
|
|
2016
|
93 |
C |
p. 386-396
11 p.
|
artikel
|
| 19 |
Experimental investigation of the overall residence time of pebbles in a pebble bed reactor (PBR) using radioactive pebble
|
Khane, Vaibhav
|
|
2016
|
93 |
C |
p. 267-276
10 p.
|
artikel
|
| 20 |
Experimental results on the breakaway oxidation of the E110 cladding alloy under high-temperature isothermal conditions
|
Perez-Feró, Erzsébet
|
|
2016
|
93 |
C |
p. 89-95
7 p.
|
artikel
|
| 21 |
Influence of second phase particles on corrosion resistance of N36 alloy in superheated steam
|
Chen, Liang
|
|
2016
|
93 |
C |
p. 84-88
5 p.
|
artikel
|
| 22 |
Multiple lines of evidence for performance of the canister and waste form in long-term nuclear waste disposal: Reviews
|
Ahn, Tae M.
|
|
2016
|
93 |
C |
p. 343-350
8 p.
|
artikel
|
| 23 |
Neutronic study of a new generation of the small modular pressurized water reactor using Monte-Carlo simulation
|
Erfaninia, Ali
|
|
2016
|
93 |
C |
p. 218-230
13 p.
|
artikel
|
| 24 |
On the improvements in neutronics analysis of the unit cell for the pebble-bed fluoride-salt-cooled high-temperature reactor
|
Li, Zhifeng
|
|
2016
|
93 |
C |
p. 287-296
10 p.
|
artikel
|
| 25 |
Post-Cold War civilian nuclear cooperation and implications for nuclear nonproliferation
|
Nguyen, Viet Phuong
|
|
2016
|
93 |
C |
p. 246-259
14 p.
|
artikel
|
| 26 |
Properties of alkali-activated slag-fly ash-metakaolin hydroceramics for immobilizing of simulated sodium-bearing waste
|
Wang, Jin
|
|
2016
|
93 |
C |
p. 12-17
6 p.
|
artikel
|
| 27 |
Reassessment of the generic assumptions applied to the conventional analysis of the reactivity insertion accident in the MTRs using a novel coupled code
|
Vadi, Roozbeh
|
|
2016
|
93 |
C |
p. 96-115
20 p.
|
artikel
|
| 28 |
Reloading pattern optimization of VVER-1000 reactors (in transient cycles) using imperialist competitive algorithm
|
Rahmani, Yashar
|
|
2016
|
93 |
C |
p. 327-342
16 p.
|
artikel
|
| 29 |
Scope of Pb-Sn binary alloys as gamma rays shielding material
|
Kaur, Sarpreet
|
|
2016
|
93 |
C |
p. 277-286
10 p.
|
artikel
|
| 30 |
Sensitivity analyses of the use of different reflector materials on the neutronics parameters of Tehran research reactor
|
Khoshahval, Farrokh
|
|
2016
|
93 |
C |
p. 351-361
11 p.
|
artikel
|
| 31 |
Shaking table model tests of concrete containment vessel (CCV) for CPR1000 nuclear power plant
|
Liu, Jun
|
|
2016
|
93 |
C |
p. 186-204
19 p.
|
artikel
|
| 32 |
Simulating and evaluating the pressurizer dynamic behavior in various sizes
|
Baghban, Ghonche
|
|
2016
|
93 |
C |
p. 406-417
12 p.
|
artikel
|
| 33 |
Simulation of early phase radioactivity of CPR1000 plant under LOCAs based on RELAP5-3D core engineering simulator
|
Ni, Xinghe
|
|
2016
|
93 |
C |
p. 47-58
12 p.
|
artikel
|
| 34 |
Strategies and dismantling solutions for RPV internals of Trino NPP
|
Maggini, A.
|
|
2016
|
93 |
C |
p. 67-75
9 p.
|
artikel
|
| 35 |
The decision making method of task arrangement based on analytic hierarchy process for nuclear safety in radiation field
|
Li, Meng-kun
|
|
2016
|
93 |
C |
p. 318-326
9 p.
|
artikel
|
| 36 |
The influence of Xe-135m on steady-state xenon worth in thermal molten salt reactors
|
Eades, Michael J.
|
|
2016
|
93 |
C |
p. 397-405
9 p.
|
artikel
|
| 37 |
Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor
|
Feng, Tangtao
|
|
2016
|
93 |
C |
p. 231-237
7 p.
|
artikel
|
| 38 |
The utilization of thorium in Generation IV reactors
|
György, H.
|
|
2016
|
93 |
C |
p. 306-317
12 p.
|
artikel
|
| 39 |
Validation of RELAP5/MOD3.3 for subcooled boiling, flashing and condensation in a vertical annulus
|
Fullmer, William D.
|
|
2016
|
93 |
C |
p. 205-217
13 p.
|
artikel
|
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