| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accuracy of thorium cross section of JENDL-4.0 library in thorium based fuel core evaluation
|
Vu, Thanh Mai
|
|
2013
|
57 |
C |
p. 173-178
6 p.
|
artikel
|
| 2 |
A CFD based approach for thermal hydraulic design of main vessel cooling system of pool type fast reactors
|
Vivek, V.
|
|
2013
|
57 |
C |
p. 269-279
11 p.
|
artikel
|
| 3 |
A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
|
Ochoa, R.
|
|
2013
|
57 |
C |
p. 32-40
9 p.
|
artikel
|
| 4 |
Analysis of surface contributions to external doses in a radioactively contaminated urban environment designed by the EMRAS-2 Urban Areas Working Group
|
Hwang, Won Tae
|
|
2013
|
57 |
C |
p. 179-184
6 p.
|
artikel
|
| 5 |
An inverse calculation technique for optimization of gamma ray shielding designs
|
Subbaiah, K.V.
|
|
2013
|
57 |
C |
p. 246-255
10 p.
|
artikel
|
| 6 |
Calculation of effective delayed neutron fraction with modified library of Monte Carlo code
|
Zhang, Liang
|
|
2013
|
57 |
C |
p. 327-333
7 p.
|
artikel
|
| 7 |
Calculation of the fuel composition and the thermo-neutronic parameters of the Bushehr’s VVER-1000 reactor during the initial startup and the first cycle using the WIMSD5-B, CITATION-LDI2 and WERL codes
|
Rahmani, Yashar
|
|
2013
|
57 |
C |
p. 68-83
16 p.
|
artikel
|
| 8 |
Characteristics of a single bubble in subcooled boiling region of a narrow rectangular channel under natural circulation
|
Zhou, Tao
|
|
2013
|
57 |
C |
p. 22-31
10 p.
|
artikel
|
| 9 |
Core design for super fast reactor with all upward flow core cooling
|
Liu, Qingjie
|
|
2013
|
57 |
C |
p. 221-229
9 p.
|
artikel
|
| 10 |
Cross sections for fast-neutron interaction with ytterbium isotopes
|
Luo, Junhua
|
|
2013
|
57 |
C |
p. 41-46
6 p.
|
artikel
|
| 11 |
Cs-137 and Cs-134 removal from radioactive ash using washing–electrokinetic equipment
|
Kim, Gye-Nam
|
|
2013
|
57 |
C |
p. 311-317
7 p.
|
artikel
|
| 12 |
Design a computational program to calculate the composition variations of nuclear materials in the reactor operations
|
Mohmmadnia, Meysam
|
|
2013
|
57 |
C |
p. 111-113
3 p.
|
artikel
|
| 13 |
Development of a model for the approximation of the neutron and photon flux in a BWR spent fuel assembly
|
Rossa, Riccardo
|
|
2013
|
57 |
C |
p. 256-262
7 p.
|
artikel
|
| 14 |
Editorial board
|
|
|
2013
|
57 |
C |
p. IFC-
1 p.
|
artikel
|
| 15 |
Effect of longitudinal pitch on convective heat transfer in crossflow over in-line tube banks
|
Kim, Taewan
|
|
2013
|
57 |
C |
p. 209-215
7 p.
|
artikel
|
| 16 |
Energy-higher order mode analyses in Feynman-α method
|
Yamamoto, Toshihiro
|
|
2013
|
57 |
C |
p. 84-91
8 p.
|
artikel
|
| 17 |
Evaluation of compressible flow in spherical fueled reactors using the porous media model
|
Pilehvar, A.F.
|
|
2013
|
57 |
C |
p. 185-194
10 p.
|
artikel
|
| 18 |
Feasibility of identifying leaking fuel rods using gamma tomography
|
Holcombe, Scott
|
|
2013
|
57 |
C |
p. 334-340
7 p.
|
artikel
|
| 19 |
Flattening of burnup reactivity in long-life prismatic HTGR by particle type burnable poisons
|
Obara, Toru
|
|
2013
|
57 |
C |
p. 216-220
5 p.
|
artikel
|
| 20 |
Gamma transport and diffusion calculation capability coupled with neutron transport simulation in KARMA 1.2
|
Kim, Kang-Seog
|
|
2013
|
57 |
C |
p. 59-67
9 p.
|
artikel
|
| 21 |
Heat conduction in nuclear fuel by the Kirchhoff transformation
|
Tomatis, Daniele
|
|
2013
|
57 |
C |
p. 100-105
6 p.
|
artikel
|
| 22 |
In-core fuel management for AHWR
|
Thakur, Amit
|
|
2013
|
57 |
C |
p. 47-58
12 p.
|
artikel
|
| 23 |
Investigation of PWR core optimization using harmony search algorithms
|
Aghaie, M.
|
|
2013
|
57 |
C |
p. 1-15
15 p.
|
artikel
|
| 24 |
Methodologies for an improved prediction of the isotopic content in high burnup samples. Application to Vandellós-II reactor core
|
Martínez, J.S.
|
|
2013
|
57 |
C |
p. 199-208
10 p.
|
artikel
|
| 25 |
Multi-objective loading pattern enhancement of PWR based on the Discrete Firefly Algorithm
|
Poursalehi, N.
|
|
2013
|
57 |
C |
p. 151-163
13 p.
|
artikel
|
| 26 |
Numerical approach to calculate the decay heat of actinides for short cooling time
|
Nafee, S.S.
|
|
2013
|
57 |
C |
p. 304-310
7 p.
|
artikel
|
| 27 |
Numerical simulation of fragmentation of melt drop triggered by external pressure pulse in vapor explosions
|
Zhou, Yuan
|
|
2013
|
57 |
C |
p. 92-99
8 p.
|
artikel
|
| 28 |
On the dependence of the noise amplitude on the correlation length of inlet temperature fluctuations in PWRs
|
Zylbersztejn, F.
|
|
2013
|
57 |
C |
p. 134-141
8 p.
|
artikel
|
| 29 |
Optimization of designing the core fuel loading pattern in a VVER-1000 nuclear power reactor using the genetic algorithm
|
Rafiei Karahroudi, M.
|
|
2013
|
57 |
C |
p. 142-150
9 p.
|
artikel
|
| 30 |
Photoneutron spectrum estimation and its experimental validation using neutron REM (Roentgen Equivalent in Man) detector
|
Eshwarappa, K.M.
|
|
2013
|
57 |
C |
p. 130-133
4 p.
|
artikel
|
| 31 |
Prediction of palladium-103 production using the Monte Carlo code MCNPX
|
Mahmodi, Mahbobeh
|
|
2013
|
57 |
C |
p. 195-198
4 p.
|
artikel
|
| 32 |
Production of medical radioisotope 153Sm in the Tehran Research Reactor (TRR) through theoretical calculations and practical tests
|
Forughi, Sh.
|
|
2013
|
57 |
C |
p. 16-21
6 p.
|
artikel
|
| 33 |
Quantitative estimation of the human error probability during soft control operations
|
Lee, Seung Jun
|
|
2013
|
57 |
C |
p. 318-326
9 p.
|
artikel
|
| 34 |
Reactor power measurement by gamma and neutron radiation in Heavy Water Zero Power Reactor (HWZPR)
|
jalali, Majid
|
|
2013
|
57 |
C |
p. 368-374
7 p.
|
artikel
|
| 35 |
Sensitivity analysis on the effect of software-induced common cause failure probability in the computer-based reactor trip system unavailability
|
Kamyab, Shahabeddin
|
|
2013
|
57 |
C |
p. 294-303
10 p.
|
artikel
|
| 36 |
Sensitivity study on the counter-current flow limitation in the DEG LBLOCA with the TRACE code
|
Chen, Chun-Yu
|
|
2013
|
57 |
C |
p. 121-129
9 p.
|
artikel
|
| 37 |
Simulation of neutron radiograph images at the Neutron Radiography Reactor
|
Morgan, Sarah W.
|
|
2013
|
57 |
C |
p. 341-349
9 p.
|
artikel
|
| 38 |
Solution of 3D multigroup, linearly anisotropic scattering, criticality problems by the A N boundary-element response-matrix method
|
Giusti, V.
|
|
2013
|
57 |
C |
p. 350-367
18 p.
|
artikel
|
| 39 |
Study of iodine removal efficiency in self-priming venturi scrubber
|
Ali, Majid
|
|
2013
|
57 |
C |
p. 263-268
6 p.
|
artikel
|
| 40 |
The comparison of designed water-cooled and air-cooled passive residual heat removal system for 300MW nuclear power plant during the feed-water line break scenario
|
Wang, Mingjun
|
|
2013
|
57 |
C |
p. 164-172
9 p.
|
artikel
|
| 41 |
The effects of operational and design parameters on the tolerance of ADSR fuel pin cladding to beam interruptions
|
Ahmad, Ali
|
|
2013
|
57 |
C |
p. 114-120
7 p.
|
artikel
|
| 42 |
The implementation of a simplified spherical harmonics semi-analytic nodal method in PANTHER
|
Hall, S.K.
|
|
2013
|
57 |
C |
p. 280-293
14 p.
|
artikel
|
| 43 |
Uncertainty and sensitivity analyses applied to the DRAGONv4.05 code lattice calculations and based on JENDL-4 data
|
Hernández-Solís, Augusto
|
|
2013
|
57 |
C |
p. 230-245
16 p.
|
artikel
|
| 44 |
Utilization of boron oxide glass and epoxy/ilmenite assembly as two layer shield
|
Gaber, F.A.
|
|
2013
|
57 |
C |
p. 106-110
5 p.
|
artikel
|
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