| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A hybrid approach to quantify software reliability in nuclear safety systems
|
Arun Babu, P.
|
|
2012
|
50 |
C |
p. 133-140
8 p.
|
artikel
|
| 2 |
Analytical solutions of the molten salt reactor equations
|
Pázsit, I.
|
|
2012
|
50 |
C |
p. 206-214
9 p.
|
artikel
|
| 3 |
A new random distribution method to simulate PBM type reactors with MCNP
|
Hosseini, S.A.
|
|
2012
|
50 |
C |
p. 215-219
5 p.
|
artikel
|
| 4 |
Assessment of the total effective dose equivalent for accidental release from the Tehran Research Reactor
|
Anvari, Akbar
|
|
2012
|
50 |
C |
p. 251-255
5 p.
|
artikel
|
| 5 |
Bayesian inference along Markov Chain Monte Carlo approach for PWR core loading pattern optimization
|
Haghighattalab, A.
|
|
2012
|
50 |
C |
p. 150-157
8 p.
|
artikel
|
| 6 |
Biological shield design for a 10MeV Rhodotron
|
Khalafi, H.
|
|
2012
|
50 |
C |
p. 111-116
6 p.
|
artikel
|
| 7 |
Coupled neutronic thermal–hydraulic transient analysis of accidents in PWRs
|
Aghaie, M.
|
|
2012
|
50 |
C |
p. 158-166
9 p.
|
artikel
|
| 8 |
Determination of radial and axial neutron flux distribution in irradiation channel of NIRR-1 using foil activation technique
|
Musa, Y.
|
|
2012
|
50 |
C |
p. 50-55
6 p.
|
artikel
|
| 9 |
Developing a computational tool for predicting physical parameters of a typical VVER-1000 core based on artificial neural network
|
Mirvakili, S.M.
|
|
2012
|
50 |
C |
p. 82-93
12 p.
|
artikel
|
| 10 |
Development of Fuel ROd Behavior Analysis code (FROBA) and its application to AP1000
|
Yu, Hongxing
|
|
2012
|
50 |
C |
p. 8-17
10 p.
|
artikel
|
| 11 |
Dynamic simulation of once-through steam generator with concentric annuli tube
|
Zhu, Jingyan
|
|
2012
|
50 |
C |
p. 185-198
14 p.
|
artikel
|
| 12 |
Editorial board
|
|
|
2012
|
50 |
C |
p. IFC-
1 p.
|
artikel
|
| 13 |
Experimental and numerical study for a siphon breaker design of a research reactor
|
Seo, Kyoungwoo
|
|
2012
|
50 |
C |
p. 94-102
9 p.
|
artikel
|
| 14 |
Experimental study of two phase flow instability in parallel narrow rectangular channels
|
Yuan, Zhou
|
|
2012
|
50 |
C |
p. 103-110
8 p.
|
artikel
|
| 15 |
Further improving LBLOCA resistance of CANDU cooled by light water
|
Popov, Alexi V.
|
|
2012
|
50 |
C |
p. 256-262
7 p.
|
artikel
|
| 16 |
Hot spot identification by sensitivity analysis and probabilistic inference methods: Demonstration exercise
|
Gandini, A.
|
|
2012
|
50 |
C |
p. 175-184
10 p.
|
artikel
|
| 17 |
Modeling of BWR Inter-Ramp Project experiments by means of TRANSURANUS code
|
Rozzia, Davide
|
|
2012
|
50 |
C |
p. 238-250
13 p.
|
artikel
|
| 18 |
Monte Carlo method with complex weights for neutron leakage-corrected calculations and anisotropic diffusion coefficient generations
|
Yamamoto, Toshihiro
|
|
2012
|
50 |
C |
p. 141-149
9 p.
|
artikel
|
| 19 |
MOX fuel use in a BWR with extended power up-rate
|
Ramon Ramirez, J.
|
|
2012
|
50 |
C |
p. 63-70
8 p.
|
artikel
|
| 20 |
Natural radionuclide content of disposed phosphogypsum as TENORM produced from phosphorus fertilizer industry in Turkey
|
Gezer, F.
|
|
2012
|
50 |
C |
p. 33-37
5 p.
|
artikel
|
| 21 |
Neutronic analysis of HPLWR fuel assembly cluster
|
Tashakor, S.
|
|
2012
|
50 |
C |
p. 38-43
6 p.
|
artikel
|
| 22 |
Optimizing a gap conductance model applicable to VVER-1000 thermal–hydraulic model
|
Rahgoshay, M.
|
|
2012
|
50 |
C |
p. 263-267
5 p.
|
artikel
|
| 23 |
PSA based vulnerability and protectability analysis for NPPs
|
Gopika, V.
|
|
2012
|
50 |
C |
p. 232-237
6 p.
|
artikel
|
| 24 |
Radionuclide migration through an unsaturated clay buffer under thermal and hydraulic gradients for a nuclear waste repository
|
Cho, Won-Jin
|
|
2012
|
50 |
C |
p. 71-81
11 p.
|
artikel
|
| 25 |
Relative evaluation on decommissioning accident scenarios of nuclear facilities
|
Jeong, Kwan-Seong
|
|
2012
|
50 |
C |
p. 268-270
3 p.
|
artikel
|
| 26 |
Source term evaluation of two loop PWR under hypothetical severe accidents
|
Mehboob, Khurram
|
|
2012
|
50 |
C |
p. 271-284
14 p.
|
artikel
|
| 27 |
Startup of “CANDLE” burnup in a Gas-cooled Fast Reactor using Monte Carlo method
|
Kheradmand Saadi, M.
|
|
2012
|
50 |
C |
p. 44-49
6 p.
|
artikel
|
| 28 |
Studies of fuel loading pattern optimization for a typical pressurized water reactor (PWR) using improved pivot particle swarm method
|
Liu, Shichang
|
|
2012
|
50 |
C |
p. 117-125
9 p.
|
artikel
|
| 29 |
The development of natural circulation operation support program for ship nuclear power machinery
|
Hao, Jianli
|
|
2012
|
50 |
C |
p. 199-205
7 p.
|
artikel
|
| 30 |
The impact of americium on transients in the European Lead-cooled SYstem ELSY loaded with nitride fuel
|
Tesinsky, Milan
|
|
2012
|
50 |
C |
p. 56-62
7 p.
|
artikel
|
| 31 |
The optimum design of power distribution for pressurized water reactor
|
Dai, Chunhui
|
|
2012
|
50 |
C |
p. 126-132
7 p.
|
artikel
|
| 32 |
Thermal and mechanical characteristics of the moderator cell in a cold neutron source
|
Sun, Shuo
|
|
2012
|
50 |
C |
p. 1-7
7 p.
|
artikel
|
| 33 |
Three-dimensional transport calculation of multiple alpha modes in subcritical systems
|
Kópházi, József
|
|
2012
|
50 |
C |
p. 167-174
8 p.
|
artikel
|
| 34 |
Validation of energy moments from the one-dimensional energy dependent neutron diffusion equation, MCNP5 and Attila-7.1.0 with the GODIVA experiment
|
Crawford, Douglas S.
|
|
2012
|
50 |
C |
p. 220-231
12 p.
|
artikel
|
| 35 |
Verification of analytic energy moments for the one-dimensional energy dependent neutron diffusion equation with MCNP5 and Attila-7.1.0
|
Crawford, Douglas S.
|
|
2012
|
50 |
C |
p. 18-32
15 p.
|
artikel
|
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