| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of regularly perturbed lattices and reaction rate distributions from TIC experiments for X7 lattices
|
Ramakrishna, A.
|
|
2011
|
38 |
7 |
p. 1623-1644
22 p.
|
artikel
|
| 2 |
Applying mechanistic models to reliability evaluation of mechanical components – An illustration
|
Hari Prasad, M.
|
|
2011
|
38 |
7 |
p. 1447-1451
5 p.
|
artikel
|
| 3 |
A statistically-engineered approach for assessing ageing effects on thermal-hydraulic elements for CANDU reactors
|
Choi, Yong Won
|
|
2011
|
38 |
7 |
p. 1527-1544
18 p.
|
artikel
|
| 4 |
Benchmark results for the critical slab and sphere problem in one-speed neutron transport theory
|
Rawat, Ajay
|
|
2011
|
38 |
7 |
p. 1658-1661
4 p.
|
artikel
|
| 5 |
Building the nodal nuclear data dependences in a many-dimensional state-variable space
|
Dufek, Jan
|
|
2011
|
38 |
7 |
p. 1569-1577
9 p.
|
artikel
|
| 6 |
CFD investigation of flow inversion in typical MTR research reactor undergoing thermal–hydraulic transients
|
Salama, Amgad
|
|
2011
|
38 |
7 |
p. 1578-1592
15 p.
|
artikel
|
| 7 |
Determination of transmission factors of concretes with different water/cement ratio, curing condition, and dosage of cement and air entraining agent
|
Şahin, Remzi
|
|
2011
|
38 |
7 |
p. 1505-1511
7 p.
|
artikel
|
| 8 |
Development of a maintenance effectiveness monitoring program for CANDU reactors
|
Jerng, Dong Wook
|
|
2011
|
38 |
7 |
p. 1512-1518
7 p.
|
artikel
|
| 9 |
Editorial board
|
|
|
2011
|
38 |
7 |
p. IFC-
1 p.
|
artikel
|
| 10 |
Effects of fuel type on the safety characteristics of a sodium-cooled fast reactor
|
Sumner, Tyler
|
|
2011
|
38 |
7 |
p. 1559-1568
10 p.
|
artikel
|
| 11 |
Evaluation of dominant time-eigenvalues of neutron transport equation by Meyer’s sub-space iterations
|
Gupta, Anurag
|
|
2011
|
38 |
7 |
p. 1680-1686
7 p.
|
artikel
|
| 12 |
Extension of core life-time in fast breeder reactor by introducing inner blanket and doping minor actinides
|
Hamase, Erina
|
|
2011
|
38 |
7 |
p. 1496-1504
9 p.
|
artikel
|
| 13 |
Feasibility study of photo-neutron flux in various irradiation channels of Ghana MNSR using a Monte Carlo code
|
Birikorang, S.A.
|
|
2011
|
38 |
7 |
p. 1593-1597
5 p.
|
artikel
|
| 14 |
Identification of pressurized water reactor transient using template matching
|
Lin, Chaung
|
|
2011
|
38 |
7 |
p. 1662-1666
5 p.
|
artikel
|
| 15 |
Influence of chemical binding on the neutron width Γn
|
Djafri, D.E.
|
|
2011
|
38 |
7 |
p. 1676-1679
4 p.
|
artikel
|
| 16 |
Integrated control system responses during load rejection transient for Lungmen ABWR Plant
|
Ma, Shaoshih
|
|
2011
|
38 |
7 |
p. 1458-1472
15 p.
|
artikel
|
| 17 |
Investigation of axial power gradients near a control rod tip
|
Loberg, John
|
|
2011
|
38 |
7 |
p. 1609-1615
7 p.
|
artikel
|
| 18 |
Measurement of thermal neutron and resonance integral cross sections of the reaction 51V(n,γ)52V using a 20 Ci Am–Be isotopic neutron source
|
Agbemava, S.E.
|
|
2011
|
38 |
7 |
p. 1616-1622
7 p.
|
artikel
|
| 19 |
Optimization treatment of point-wise nuclear data in Monte Carlo criticality and burnup calculations
|
Liu, Yuxuan
|
|
2011
|
38 |
7 |
p. 1489-1495
7 p.
|
artikel
|
| 20 |
Prediction of the neutrons subcritical multiplication using the diffusion hybrid equation with external neutron sources
|
da Silva, Adilson Costa
|
|
2011
|
38 |
7 |
p. 1667-1675
9 p.
|
artikel
|
| 21 |
RETRAN analysis results of feedwater pump trip transient for Lungmen ABWR Plant
|
Ma, Shaoshih
|
|
2011
|
38 |
7 |
p. 1598-1608
11 p.
|
artikel
|
| 22 |
Spatial stabilization of Advanced Heavy Water Reactor
|
Shimjith, S.R.
|
|
2011
|
38 |
7 |
p. 1545-1558
14 p.
|
artikel
|
| 23 |
The neutronic design of a critical lead reflected zero-power reference core for on-line subcriticality measurements in Accelerator Driven Systems
|
Uyttenhove, W.
|
|
2011
|
38 |
7 |
p. 1519-1526
8 p.
|
artikel
|
| 24 |
Theoretical estimates of cross sections for neutron–nucleus collisions
|
Mukhopadhyay, Tapan
|
|
2011
|
38 |
7 |
p. 1452-1457
6 p.
|
artikel
|
| 25 |
Validation of reactor noise linear stability methods by means of advanced stochastic differential equation models
|
Munoz-Cobo, J.L.
|
|
2011
|
38 |
7 |
p. 1473-1488
16 p.
|
artikel
|
| 26 |
Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle
|
Sun, Kaichao
|
|
2011
|
38 |
7 |
p. 1645-1657
13 p.
|
artikel
|
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