| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of thermal–hydraulic parameters of WWER-1000 containment in a large break LOCA
|
Noori-Kalkhoran, Omid
|
|
2014
|
68 |
C |
p. 101-111
11 p.
|
artikel
|
| 2 |
An analytical investigation of loop seal clearings for the SBLOCA tests
|
Kim, Yeon-Sik
|
|
2014
|
68 |
C |
p. 30-42
13 p.
|
artikel
|
| 3 |
A new power mapping method based on ordinary kriging and determination of optimal detector location strategy
|
Peng, Xingjie
|
|
2014
|
68 |
C |
p. 118-123
6 p.
|
artikel
|
| 4 |
An immersed body method for coupled neutron transport and thermal hydraulic simulations of PWR assemblies
|
Jewer, S.
|
|
2014
|
68 |
C |
p. 124-135
12 p.
|
artikel
|
| 5 |
A numerical approach based on Haar wavelet operational method to solve neutron point kinetics equation involving imposed reactivity insertions
|
Patra, A.
|
|
2014
|
68 |
C |
p. 112-117
6 p.
|
artikel
|
| 6 |
A practical implementation of the higher-order transverse-integrated nodal diffusion method
|
Prinsloo, Rian H.
|
|
2014
|
68 |
C |
p. 70-88
19 p.
|
artikel
|
| 7 |
Atmospheric dispersion modeling and radiological safety analysis for a hypothetical accident of Ghana Research Reactor-1 (GHARR-1)
|
Muswema, J.L.
|
|
2014
|
68 |
C |
p. 239-246
8 p.
|
artikel
|
| 8 |
A verification problem for thermal hydraulics systems codes dealing with twin, parallel-boiling and inverted U-tubes condensing channels
|
Lazarte, Alejandro I.
|
|
2014
|
68 |
C |
p. 163-171
9 p.
|
artikel
|
| 9 |
Bond graph representation of nuclear reactor point kinetics and nearly incompressible thermal hydraulics
|
Sosnovsky, Eugeny
|
|
2014
|
68 |
C |
p. 15-29
15 p.
|
artikel
|
| 10 |
Description of a stable scheme for steady-state coupled Monte Carlo–thermal–hydraulic calculations
|
Dufek, Jan
|
|
2014
|
68 |
C |
p. 1-3
3 p.
|
artikel
|
| 11 |
Design of an epithermal neutron beam for BNCT in thermal column of Tehran research reactor
|
Kasesaz, Yaser
|
|
2014
|
68 |
C |
p. 234-238
5 p.
|
artikel
|
| 12 |
Dynamic modeling of steam water system of prototype fast breeder reactor using RELAP code
|
Sharma, Prashant
|
|
2014
|
68 |
C |
p. 209-219
11 p.
|
artikel
|
| 13 |
Editorial board
|
|
|
2014
|
68 |
C |
p. IFC-
1 p.
|
artikel
|
| 14 |
Effects of fuel particle size distributions on neutron transport in stochastic media
|
Liang, Chao
|
|
2014
|
68 |
C |
p. 146-156
11 p.
|
artikel
|
| 15 |
Extension for load-follow operation of PWR core by using single- or multi-variable control of state-feedback
|
Li, Gang
|
|
2014
|
68 |
C |
p. 183-192
10 p.
|
artikel
|
| 16 |
Feasibility analysis of aggressive cooldown in OPR-1000 nuclear power plants
|
Kim, Man Cheol
|
|
2014
|
68 |
C |
p. 89-95
7 p.
|
artikel
|
| 17 |
Fine-mesh deterministic modeling of PWR fuel assemblies: Proof-of-principle of coupled neutronic/thermal–hydraulic calculations
|
Jareteg, Klas
|
|
2014
|
68 |
C |
p. 247-256
10 p.
|
artikel
|
| 18 |
Finite difference analysis of the transient temperature profile within GHARR-1 fuel element
|
Annafi, T.A.
|
|
2014
|
68 |
C |
p. 204-208
5 p.
|
artikel
|
| 19 |
Gamma radiation shielding and optical properties measurements of zinc bismuth borate glasses
|
Yasaka, P.
|
|
2014
|
68 |
C |
p. 4-9
6 p.
|
artikel
|
| 20 |
Hybrid subgroup decomposition method for solving fine-group eigenvalue transport problems
|
Yasseri, Saam
|
|
2014
|
68 |
C |
p. 136-145
10 p.
|
artikel
|
| 21 |
Local impact effects on concrete target due to missile: An empirical and numerical approach
|
Ranjan, Rajiv
|
|
2014
|
68 |
C |
p. 262-275
14 p.
|
artikel
|
| 22 |
Measurement of control rod reactivity and shut down margin of 3 MW TRIGA Mark-II research reactor using analogue and digital I&C system
|
Salam, M.A.
|
|
2014
|
68 |
C |
p. 257-261
5 p.
|
artikel
|
| 23 |
Modeling and control simulation of the China CLEAR-IB
|
Yan, Shoujun
|
|
2014
|
68 |
C |
p. 53-60
8 p.
|
artikel
|
| 24 |
Modeling and LQG/LTR control for power and axial power difference of load-follow PWR core
|
Li, Gang
|
|
2014
|
68 |
C |
p. 193-203
11 p.
|
artikel
|
| 25 |
Optimization of thermal neutron flux in an irradiator assembly with different isotopic sources
|
Osman, A.M.
|
|
2014
|
68 |
C |
p. 10-14
5 p.
|
artikel
|
| 26 |
Parameter analysis of the neutron point kinetics equations with feedback temperature effects
|
El_Tokhy, Mohamed S.
|
|
2014
|
68 |
C |
p. 228-233
6 p.
|
artikel
|
| 27 |
Photon attenuation coefficients of thermoluminescent dosimetric materials by Geant4 toolkit, XCOM program and experimental data: A comparison study
|
Singh, Vishwanath P.
|
|
2014
|
68 |
C |
p. 96-100
5 p.
|
artikel
|
| 28 |
Radiation effects on structural properties of glass by using ultrasonic techniques and FTIR spectroscopy: A comparison between local sand and SiO2
|
Laopaiboon, Raewat
|
|
2014
|
68 |
C |
p. 220-227
8 p.
|
artikel
|
| 29 |
Terrain and building effects on the transport of radioactive material at a nuclear site
|
Jeong, Hyojoon
|
|
2014
|
68 |
C |
p. 157-162
6 p.
|
artikel
|
| 30 |
The OpenMOC method of characteristics neutral particle transport code
|
Boyd, William
|
|
2014
|
68 |
C |
p. 43-52
10 p.
|
artikel
|
| 31 |
Three-dimensional high order nodal code, ACNECH, for the neutronic modeling of hexagonal-z geometry
|
Poursalehi, N.
|
|
2014
|
68 |
C |
p. 172-182
11 p.
|
artikel
|
| 32 |
Weight optimal design of the primary coolant system for a pressurized water reactor
|
Chen, Lei
|
|
2014
|
68 |
C |
p. 61-69
9 p.
|
artikel
|
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