| no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
| 1 |
Adjoint Monte Carlo neutron transport using cross-section probability table representation
|
Diop, Cheikh M’Backé
|
|
2010
|
37 |
9 |
p. 1186-1196
11 p.
|
article
|
| 2 |
A probabilistic study of the effect of retardation factor uncertainty using a compartment model for radionuclide release into the biosphere
|
Hagues, A.W.
|
|
2010
|
37 |
9 |
p. 1197-1207
11 p.
|
article
|
| 3 |
A sensitivity study on fast reactor scenarios with various conversion ratios
|
Jeong, Chang Joon
|
|
2010
|
37 |
9 |
p. 1229-1235
7 p.
|
article
|
| 4 |
CANDU refuelling optimization by successive two-step mathematical programming – I: MILP models for refuelling channel selection
|
Zhang, Shaohong
|
|
2010
|
37 |
9 |
p. 1146-1159
14 p.
|
article
|
| 5 |
Computational fluid dynamic analysis of core bypass flow phenomena in a prismatic VHTR
|
Sato, Hiroyuki
|
|
2010
|
37 |
9 |
p. 1172-1185
14 p.
|
article
|
| 6 |
Editorial board
|
|
|
2010
|
37 |
9 |
p. IFC-
1 p.
|
article
|
| 7 |
Fluorination of UF4 in a mini-tapered fluidized bed and mathematical modeling
|
Khani, M.H.
|
|
2010
|
37 |
9 |
p. 1241-1247
7 p.
|
article
|
| 8 |
Investigating the effect of task complexities on the response time of human operators to perform the emergency tasks of nuclear power plants
|
Park, Jinkyun
|
|
2010
|
37 |
9 |
p. 1160-1171
12 p.
|
article
|
| 9 |
[No title]
|
Weaver, D.R.
|
|
2010
|
37 |
9 |
p. 1261-1262
2 p.
|
article
|
| 10 |
SHTV, as a technique for core calculation using spatial homogenization and temperature variation
|
Moghaddam, Nader Maleki
|
|
2010
|
37 |
9 |
p. 1129-1138
10 p.
|
article
|
| 11 |
Subcritical multiplication factor and source efficiency in accelerator-driven system
|
Shahbunder, Hesham
|
|
2010
|
37 |
9 |
p. 1214-1222
9 p.
|
article
|
| 12 |
Sub-critical reactor kinetics analysis using incomplete gamma functions and binomial expansions
|
Sathiyasheela, T.
|
|
2010
|
37 |
9 |
p. 1248-1253
6 p.
|
article
|
| 13 |
The use of WIMS and CITATION codes in fuel loading required for the conversion of HEU MNSR core to LEU
|
Azande, T.S.
|
|
2010
|
37 |
9 |
p. 1223-1228
6 p.
|
article
|
| 14 |
Transport model based on three-dimensional cross-section generation for TRIGA core analysis
|
Kriangchaiporn, N.
|
|
2010
|
37 |
9 |
p. 1254-1260
7 p.
|
article
|
| 15 |
Use of the local Pu-239 concentration as an indicator of burnup spectral history in DYN3D
|
Bilodid, I.
|
|
2010
|
37 |
9 |
p. 1208-1213
6 p.
|
article
|
| 16 |
Validation of the Monte Carlo model supporting core conversion of the Portuguese Research Reactor (RPI) for neutron fluence rate determinations
|
Fernandes, A.C.
|
|
2010
|
37 |
9 |
p. 1139-1145
7 p.
|
article
|
| 17 |
Vapor explosions: Prediction of a critical liquid–corium velocity in vapor destabilization mechanism of corium melt in the fuel–coolant interactions – FCI
|
Arias, F.J.
|
|
2010
|
37 |
9 |
p. 1236-1240
5 p.
|
article
|
Journal description