no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
1 |
An estimate of the order of magnitude of the explosion during a core meltdown-compaction accident for heavy liquid metal fast reactors: A disquieting result updating the Bethe–Tait model
|
Arias, F.J. |
|
2015 |
79 |
C |
p. 182-189 8 p. |
article |
2 |
Assessment of safety aspects of first rod-type fuel irradiation at Tehran research reactor, Part I: Neutronic analysis
|
Safaei Arshi, S. |
|
2015 |
79 |
C |
p. 56-63 8 p. |
article |
3 |
Design and technology development for small modular reactors – Safety expectations, prospects and impediments of their deployment
|
Hidayatullah, H. |
|
2015 |
79 |
C |
p. 127-135 9 p. |
article |
4 |
Development of high-performance heavy density concrete using different aggregates for gamma-ray shielding
|
Ouda, Ahmed S. |
|
2015 |
79 |
C |
p. 48-55 8 p. |
article |
5 |
Editorial Board
|
|
|
2015 |
79 |
C |
p. IFC- 1 p. |
article |
6 |
Effect of Nu correlation uncertainty on safety margin for passive containment cooling system in AP1000
|
Yu, Yu |
|
2015 |
79 |
C |
p. 1-7 7 p. |
article |
7 |
Estimation of self-shielded cross section by employing interference correction factors in subgroup method
|
Sohail, Muhammad |
|
2015 |
79 |
C |
p. 150-157 8 p. |
article |
8 |
Evaluation of an FPGA-based fuzzy logic control of feed-water for ABWR under automatic power regulating
|
Lu, Jun-Jen |
|
2015 |
79 |
C |
p. 22-31 10 p. |
article |
9 |
Evaluation of candidate materials for SCWR turbine and balance of plant shielding
|
Kebwaro, Jeremiah Monari |
|
2015 |
79 |
C |
p. 136-141 6 p. |
article |
10 |
Experimental study on the sub-atmospheric loop heat pipe passive cooling system for spent fuel pool
|
Xiong, Zhenqin |
|
2015 |
79 |
C |
p. 40-47 8 p. |
article |
11 |
Ground deposition assessment of radionuclides following a hypothetical release from Ghana Research Reactor-1 (GHARR-1) using atmospheric dispersion model
|
Birikorang, S.A. |
|
2015 |
79 |
C |
p. 96-103 8 p. |
article |
12 |
Loss of coolant accident analyses on multi purpose research reactor by RELAP5/MOD3.2 code
|
Karimpour, Masoumeh |
|
2015 |
79 |
C |
p. 158-166 9 p. |
article |
13 |
MCNP6 simulations of gamma line emissions from fission products and their comparisons to plutonium and uranium measurements
|
Andrews, M.T. |
|
2015 |
79 |
C |
p. 87-95 9 p. |
article |
14 |
Natural convection heat transfer in corium pools: A review work of experimental studies
|
Zhang, Luteng |
|
2015 |
79 |
C |
p. 167-181 15 p. |
article |
15 |
On-line fault detection of a fuel rod temperature measurement sensor in a nuclear reactor core using ANNs
|
Messai, A. |
|
2015 |
79 |
C |
p. 8-21 14 p. |
article |
16 |
Preliminary thermal-hydraulic safety analysis of Tehran research reactor during fuel irradiation experiment
|
Safaei Arshi, S. |
|
2015 |
79 |
C |
p. 32-39 8 p. |
article |
17 |
Review of droplet entrainment in annular flow: Characterization of the entrained droplets
|
Berna, C. |
|
2015 |
79 |
C |
p. 64-86 23 p. |
article |
18 |
Seismic analysis of RCS with finite element model for advanced PWR
|
Tong, L.L. |
|
2015 |
79 |
C |
p. 142-149 8 p. |
article |
19 |
Sliding mode observer design for a PWR to estimate the xenon concentration & delayed neutrons precursor density based on the two point nuclear reactor model
|
Ansarifar, G.R. |
|
2015 |
79 |
C |
p. 104-114 11 p. |
article |
20 |
The influence of the condenser cooling seawater salinity changes on the thermal performance of a nuclear power plant
|
Ibrahim, Said M.A. |
|
2015 |
79 |
C |
p. 115-126 12 p. |
article |