| no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
| 1 |
A feasible core design of lead bismuth eutectic cooled CANDLE fast reactor
|
Nagata, Akito
|
|
2009
|
36 |
5 |
p. 562-566
5 p.
|
article
|
| 2 |
Analysis of three different types of blockage in a sodium flow path with the MATRA-LMR-FB code
|
Jeong, H.-Y.
|
|
2009
|
36 |
5 |
p. 583-589
7 p.
|
article
|
| 3 |
Analytical evaluation on dynamical response characteristics of reduced-moderation water reactor with tight-lattice core under natural circulation core cooling
|
Ishikawa, Nobuyuki
|
|
2009
|
36 |
5 |
p. 650-658
9 p.
|
article
|
| 4 |
An assessment of the effectiveness of fuel cycle technologies for the national energy security enhancement in the electricity sector
|
Kim, Hyun Jun
|
|
2009
|
36 |
5 |
p. 604-611
8 p.
|
article
|
| 5 |
A new optimization method based on cellular automata for VVER-1000 nuclear reactor loading pattern
|
Fadaei, Amir Hosein
|
|
2009
|
36 |
5 |
p. 659-667
9 p.
|
article
|
| 6 |
Comment on the stochastic transition matrix approach for particle transport problems in a dichotomous random medium
|
Sahni, D.C.
|
|
2009
|
36 |
5 |
p. 700-701
2 p.
|
article
|
| 7 |
Computation of some transport theory expressions for a line source in an infinite half-space
|
Loyalka, S.K.
|
|
2009
|
36 |
5 |
p. 612-619
8 p.
|
article
|
| 8 |
Development of an MCNP-tally based burnup code and validation through PWR benchmark exercises
|
El Bakkari, B.
|
|
2009
|
36 |
5 |
p. 626-633
8 p.
|
article
|
| 9 |
Development of a steady state analysis code for a molten salt reactor
|
Zhang, D.L.
|
|
2009
|
36 |
5 |
p. 590-603
14 p.
|
article
|
| 10 |
Editorial board
|
|
|
2009
|
36 |
5 |
p. IFC-
1 p.
|
article
|
| 11 |
EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors
|
Krepel, Jiri
|
|
2009
|
36 |
5 |
p. 550-561
12 p.
|
article
|
| 12 |
Fixation of radioactive chemical sludge in a matrix containing cement and additives
|
Sinha, P.K.
|
|
2009
|
36 |
5 |
p. 620-625
6 p.
|
article
|
| 13 |
Fuel rod model based on Non-Fourier heat conduction equation
|
Espinosa-Paredes, G.
|
|
2009
|
36 |
5 |
p. 680-693
14 p.
|
article
|
| 14 |
Homogeneous zones definition in deterministic codes and effect on computed neutronic parameters
|
Varvayanni, M.
|
|
2009
|
36 |
5 |
p. 567-574
8 p.
|
article
|
| 15 |
Measurement and analysis of the energy–angular distribution of secondary neutrons for 9Be at 5.9 and 6.4MeV incident neutrons
|
Chen, Jinxiang
|
|
2009
|
36 |
5 |
p. 668-675
8 p.
|
article
|
| 16 |
Modifications in SCDAP code for early phase degradation in a CANDU fuel channel
|
Mladin, M.
|
|
2009
|
36 |
5 |
p. 634-640
7 p.
|
article
|
| 17 |
Monte Carlo simulation and benchmarking of pulsed neutron experiments in variable buckling Beo systems
|
Sohrabpour, M.
|
|
2009
|
36 |
5 |
p. 547-549
3 p.
|
article
|
| 18 |
Radioactive contamination measurements of the primary sodium pipes in FBTR by gamma spectrometry
|
Jose, M.T.
|
|
2009
|
36 |
5 |
p. 641-649
9 p.
|
article
|
| 19 |
Reactivity calculation with reduction of the nuclear power fluctuations
|
Díaz, Daniel Suescún
|
|
2009
|
36 |
5 |
p. 676-679
4 p.
|
article
|
| 20 |
Shielding analysis for an Advanced Voloxidation Process with Monte Carlo calculations
|
Park, Chang Je
|
|
2009
|
36 |
5 |
p. 694-699
6 p.
|
article
|
| 21 |
TN approximation on the critical size of time-dependent, one-speed and one-dimensional neutron transport problem with anisotropic scattering
|
Öztürk, Hakan
|
|
2009
|
36 |
5 |
p. 575-582
8 p.
|
article
|
Journal description