nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
An adaptive mesh refinement approach for average current nodal expansion method in 2-D rectangular geometry
|
Poursalehi, N. |
|
2013 |
55 |
C |
p. 61-70 10 p. |
artikel |
2 |
An incident flux expansion transport theory method suitable for coupling to diffusion theory methods in hexagonal geometry
|
Hayward, Robert M. |
|
2013 |
55 |
C |
p. 279-287 9 p. |
artikel |
3 |
APOLLO2 and TRIPOLI4 solutions of the OECD VVER-1000 LEU and MOX assembly benchmark
|
Petrov, N. |
|
2013 |
55 |
C |
p. 93-107 15 p. |
artikel |
4 |
A study on evaluation of pebble flow velocity with modification of the kinematic model for pebble bed reactor
|
Kim, Song Hyun |
|
2013 |
55 |
C |
p. 322-330 9 p. |
artikel |
5 |
Comparison of photon attenuation coefficients of various barite concretes and lead by MCNP code, XCOM and experimental data
|
Shirmardi, S.P. |
|
2013 |
55 |
C |
p. 288-291 4 p. |
artikel |
6 |
Comparison of thermal scattering processing options for S(α,β) cards in MCNP
|
Čerba, Štefan |
|
2013 |
55 |
C |
p. 18-22 5 p. |
artikel |
7 |
Concept of a high temperature integrated multi-modular thermal reactor
|
Patel, Vishal |
|
2013 |
55 |
C |
p. 312-321 10 p. |
artikel |
8 |
Confirmation of accuracy of generalized power series method for the solution of point kinetics equations with feedback
|
Hamada, Yasser Mohamed |
|
2013 |
55 |
C |
p. 184-193 10 p. |
artikel |
9 |
Development of a high order and multi-dimensional nodal code, ACNEC3D, for reactor core analysis
|
Poursalehi, N. |
|
2013 |
55 |
C |
p. 211-224 14 p. |
artikel |
10 |
Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor
|
Hu, B.X. |
|
2013 |
55 |
C |
p. 302-311 10 p. |
artikel |
11 |
Double differential cross sections of light charged particle emission of n + 27Al reaction
|
Han, Yinlu |
|
2013 |
55 |
C |
p. 75-92 18 p. |
artikel |
12 |
Editorial board
|
|
|
2013 |
55 |
C |
p. IFC- 1 p. |
artikel |
13 |
Effective delayed neutron fraction and prompt neutron lifetime of Tehran research reactor mixed-core
|
Lashkari, A. |
|
2013 |
55 |
C |
p. 265-271 7 p. |
artikel |
14 |
Efficient estimation of the functional reliability of a passive system by means of an improved Line Sampling method
|
Wang, Baosheng |
|
2013 |
55 |
C |
p. 9-17 9 p. |
artikel |
15 |
Evaluation of core compositions for use in breed and burn reactors and limited-separations fuel cycles
|
Petroski, Robert |
|
2013 |
55 |
C |
p. 151-168 18 p. |
artikel |
16 |
Fractional-space law for the neutron current density
|
Espinosa-Paredes, G. |
|
2013 |
55 |
C |
p. 120-125 6 p. |
artikel |
17 |
Gas threshold pressure and gas permeability of silo concrete specimens for a low- and intermediate-level waste disposal facility in Korea
|
Kim, Juyub |
|
2013 |
55 |
C |
p. 1-8 8 p. |
artikel |
18 |
Goal based mesh adaptivity for fixed source radiation transport calculations
|
Baker, C.M.J. |
|
2013 |
55 |
C |
p. 169-183 15 p. |
artikel |
19 |
Investigation of shielding properties of some boron compounds
|
İçelli, Orhan |
|
2013 |
55 |
C |
p. 341-350 10 p. |
artikel |
20 |
Investigation on radiation shielding parameters of bismuth borosilicate glass from 1keV to 100GeV
|
Chanthima, N. |
|
2013 |
55 |
C |
p. 23-28 6 p. |
artikel |
21 |
Investigations of flow and temperature field development in bare and wire-wrapped reactor fuel pin bundles cooled by sodium
|
Govindha Rasu, N. |
|
2013 |
55 |
C |
p. 29-41 13 p. |
artikel |
22 |
Measurement of gamma attenuation for ANR end shield model using CaSO4:Dy phosphor
|
Bakshi, A.K. |
|
2013 |
55 |
C |
p. 205-210 6 p. |
artikel |
23 |
Modelling of VVER-440/213 hermetic rooms in training simulator
|
Nagy, Attila |
|
2013 |
55 |
C |
p. 272-278 7 p. |
artikel |
24 |
Monte Carlo analysis of the propagation of fusion neutrons in a high enriched uranium system
|
Difilippo, Felix C. |
|
2013 |
55 |
C |
p. 126-136 11 p. |
artikel |
25 |
Neutronic analysis of SFR core with HELIOS-2, Serpent, and DYN3D codes
|
Rachamin, R. |
|
2013 |
55 |
C |
p. 194-204 11 p. |
artikel |
26 |
Neutronic design of a very high temperature reactor core with low graphite content
|
Telésforo-Reyes, Dionisio |
|
2013 |
55 |
C |
p. 71-74 4 p. |
artikel |
27 |
Numerical investigation of thermal–hydraulic characteristics in a steam generator using a coupled primary and secondary side heat transfer model
|
Li, Yanjun |
|
2013 |
55 |
C |
p. 258-264 7 p. |
artikel |
28 |
Numerical simulations and laboratory experiments for evaluating the characteristics of pollutant transport
|
Suh, Kyung-Suk |
|
2013 |
55 |
C |
p. 55-60 6 p. |
artikel |
29 |
Optimising the energy group structure used for fusion systems
|
Morgan, L. |
|
2013 |
55 |
C |
p. 108-115 8 p. |
artikel |
30 |
Optimum burnup of BAEC TRIGA research reactor
|
Lyric, Zoairia Idris |
|
2013 |
55 |
C |
p. 225-229 5 p. |
artikel |
31 |
Performance of refractometry in quantitative estimation of isotopic concentration of heavy water in nuclear reactor
|
Dhole, K. |
|
2013 |
55 |
C |
p. 116-119 4 p. |
artikel |
32 |
Public exposure from environmental release of radioactive material under normal operation of unit-1 Bushehr nuclear power plant
|
Sohrabi, M. |
|
2013 |
55 |
C |
p. 351-358 8 p. |
artikel |
33 |
The effect of calm conditions and wind intervals in low wind speed on atmospheric dispersion factors
|
Jeong, Hyojoon |
|
2013 |
55 |
C |
p. 230-237 8 p. |
artikel |
34 |
The numerical solution of the point kinetics equation using the matrix exponential method
|
Park, Yujin |
|
2013 |
55 |
C |
p. 42-48 7 p. |
artikel |
35 |
Thermal-hydraulic analysis of SMART steam generator tube rupture using TASS/SMR-S code
|
Kim, Hee-Kyung |
|
2013 |
55 |
C |
p. 331-340 10 p. |
artikel |
36 |
Thermo-hydraulic characteristics of the helically coiled tube and the condensate heat exchanger for SMART
|
Chung, Young-Jong |
|
2013 |
55 |
C |
p. 49-54 6 p. |
artikel |
37 |
Three-dimensional Monte Carlo calculation of gas production in structural material of APEX reactor for some evaluated data files
|
Günay, Mehtap |
|
2013 |
55 |
C |
p. 292-296 5 p. |
artikel |
38 |
Time-of-flight discrimination between gamma-rays and neutrons by using artificial neural networks
|
Akkoyun, S. |
|
2013 |
55 |
C |
p. 297-301 5 p. |
artikel |
39 |
Transient analyses for lead–bismuth cooled accelerator-driven system
|
Sugawara, Takanori |
|
2013 |
55 |
C |
p. 238-247 10 p. |
artikel |
40 |
TRU management and 235U consumption minimization in fuel cycle scenarios with AP1000 and VHTRs
|
Cuvelier, Marie-Hermine M. |
|
2013 |
55 |
C |
p. 137-150 14 p. |
artikel |
41 |
Visual numerical steering in 3D AGENT code system for advanced nuclear reactor modeling and design
|
Hernandez, Hermilo |
|
2013 |
55 |
C |
p. 248-257 10 p. |
artikel |