| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A deceleration system for near-diameter spheres in pipeline transportation in a pebble bed reactor based on the resistance of a pneumatic cushion
|
Liu, Hongbing
|
|
2014
|
275 |
C |
p. 61-68
8 p.
|
artikel
|
| 2 |
Analysis of events related to cracks and leaks in the reactor coolant pressure boundary
|
Ballesteros, Antonio
|
|
2014
|
275 |
C |
p. 163-167
5 p.
|
artikel
|
| 3 |
Analysis of flow-induced vibration of steam generator tubes subjected to cross flow
|
Zhao, Wensheng
|
|
2014
|
275 |
C |
p. 375-381
7 p.
|
artikel
|
| 4 |
Analytical model for performance verification of liquid poison injection system of a nuclear reactor
|
Kansal, Anuj Kumar
|
|
2014
|
275 |
C |
p. 329-335
7 p.
|
artikel
|
| 5 |
An experimental study on local fuel–coolant interactions by delivering water into a simulated molten fuel pool
|
Cheng, Songbai
|
|
2014
|
275 |
C |
p. 133-141
9 p.
|
artikel
|
| 6 |
A novel method for in-situ estimation of time constant for core temperature monitoring thermocouples of operating reactors
|
Sylvia, J.I.
|
|
2014
|
275 |
C |
p. 154-162
9 p.
|
artikel
|
| 7 |
ASSERT-PV 3.2: Advanced subchannel thermalhydraulics code for CANDU fuel bundles
|
Rao, Y.F.
|
|
2014
|
275 |
C |
p. 69-79
11 p.
|
artikel
|
| 8 |
Assessment of subchannel code ASSERT-PV for flow-distribution predictions
|
Nava-Dominguez, A.
|
|
2014
|
275 |
C |
p. 122-132
11 p.
|
artikel
|
| 9 |
Benchmark analyses for EBR-II shutdown heat removal tests SHRT-17 and SHRT-45R
|
Mochizuki, Hiroyasu
|
|
2014
|
275 |
C |
p. 312-321
10 p.
|
artikel
|
| 10 |
Biaxial creep deformation behavior of Fe–14Cr–15Ni–Ti modified austenitic stainless steel fuel cladding tube for sodium cooled fast reactor
|
Mathew, M.D.
|
|
2014
|
275 |
C |
p. 17-22
6 p.
|
artikel
|
| 11 |
Computational and experimental studies of the flow field near the beam entrance window of a liquid metal target
|
Geža, Vadims
|
|
2014
|
275 |
C |
p. 96-106
11 p.
|
artikel
|
| 12 |
Deterioration of limestone aggregate mortars by liquid sodium in fast breeder reactor environment
|
Mohammed Haneefa, K.
|
|
2014
|
275 |
C |
p. 287-299
13 p.
|
artikel
|
| 13 |
Development of 3-D CFD methodology to investigate the transient thermal-hydraulic characteristics of coolant in a spent fuel pool
|
Chen, S.R.
|
|
2014
|
275 |
C |
p. 272-280
9 p.
|
artikel
|
| 14 |
Effects of operating conditions on molten-salt electrorefining for zirconium recovery from irradiated Zircaloy-4 cladding of pressurized water reactor
|
Park, Jaeyeong
|
|
2014
|
275 |
C |
p. 44-52
9 p.
|
artikel
|
| 15 |
Equivalent linear and nonlinear site response analysis for design and risk assessment of safety-related nuclear structures
|
Bolisetti, Chandrakanth
|
|
2014
|
275 |
C |
p. 107-121
15 p.
|
artikel
|
| 16 |
Experimental and numerical researches on collision of graphite bricks
|
Jin, Lie
|
|
2014
|
275 |
C |
p. 179-189
11 p.
|
artikel
|
| 17 |
Experimental investigation of heat transfer from a 2×2 rod bundle to supercritical pressure water
|
Wang, Han
|
|
2014
|
275 |
C |
p. 205-218
14 p.
|
artikel
|
| 18 |
Fault detection of nuclear reactors by estimation of unknown input for systems with disturbances
|
Pang, Yan
|
|
2014
|
275 |
C |
p. 91-95
5 p.
|
artikel
|
| 19 |
GTHTR300—A nuclear power plant design with 50% generating efficiency
|
Sato, Hiroyuki
|
|
2014
|
275 |
C |
p. 190-196
7 p.
|
artikel
|
| 20 |
Identification of limiting case between DBA and SBDBA (CL break area sensitivity): A new model for the boron injection system
|
Gonzalez Gonzalez, R.
|
|
2014
|
275 |
C |
p. 1-10
10 p.
|
artikel
|
| 21 |
In-core power sharing and fuel requirement study for a decommissioning Boiling Water Reactor using the linear reactivity model
|
Chen, Chung-Yuan
|
|
2014
|
275 |
C |
p. 264-271
8 p.
|
artikel
|
| 22 |
Integral effect test and code analysis on the cooling performance of the PAFS (passive auxiliary feedwater system) during an FLB (feedwater line break) accident
|
Bae, Byoung-Uhn
|
|
2014
|
275 |
C |
p. 249-263
15 p.
|
artikel
|
| 23 |
Integrated probabilistic assessment for DHC initiation, growth and leak-before-break of PHWR pressure tubes
|
Oh, Young-Jin
|
|
2014
|
275 |
C |
p. 30-43
14 p.
|
artikel
|
| 24 |
Integrity analysis of reactor pressure vessels subjected to pressurized thermal shocks by XFEM
|
González-Albuixech, V.F.
|
|
2014
|
275 |
C |
p. 336-343
8 p.
|
artikel
|
| 25 |
Leak rate models and their thermal interaction with structures for Leak-before-Break applications
|
Gill, Peter
|
|
2014
|
275 |
C |
p. 219-228
10 p.
|
artikel
|
| 26 |
Modeling strategies to compute natural circulation using CFD in a VHTR after a LOFA
|
Tung, Yu-Hsin
|
|
2014
|
275 |
C |
p. 80-90
11 p.
|
artikel
|
| 27 |
Neutronic performance of uranium nitride composite fuels in a PWR
|
Brown, Nicholas R.
|
|
2014
|
275 |
C |
p. 393-407
15 p.
|
artikel
|
| 28 |
Numerical investigation of condensing flow in the last stage of low-pressure nuclear steam turbine
|
Xinggang, Yu
|
|
2014
|
275 |
C |
p. 197-204
8 p.
|
artikel
|
| 29 |
Numerical study of the turbulent flow and vortex structures in a new lattice
|
Xiao, Hongguang
|
|
2014
|
275 |
C |
p. 344-351
8 p.
|
artikel
|
| 30 |
Potential issues related to emergency core cooling system strainers performance at boiling water reactors: Application to Cofrentes NPP (Spain)
|
Rubio, Rafael
|
|
2014
|
275 |
C |
p. 11-16
6 p.
|
artikel
|
| 31 |
Prediction of concrete compressive strength considering humidity and temperature in the construction of nuclear power plants
|
Kwon, Seung Hee
|
|
2014
|
275 |
C |
p. 23-29
7 p.
|
artikel
|
| 32 |
Probabilistic elastic-plastic analysis of cracked pipes subjected to internal pressure load
|
Mechab, B.
|
|
2014
|
275 |
C |
p. 281-286
6 p.
|
artikel
|
| 33 |
Scaling method for storage vaults based on thermal-hydraulic characteristics
|
Kim, Donghee
|
|
2014
|
275 |
C |
p. 242-248
7 p.
|
artikel
|
| 34 |
Sorption behavior of cesium from aqueous solution on magnetic hexacyanoferrate materials
|
Zhang, Hengxuan
|
|
2014
|
275 |
C |
p. 322-328
7 p.
|
artikel
|
| 35 |
Spent fuel criticality and compositions evaluation for long-term disposal in a generic cask
|
Velasquez, C.E.
|
|
2014
|
275 |
C |
p. 168-178
11 p.
|
artikel
|
| 36 |
SPHERE: Irradiation of sphere-pac fuel of UPuO2−x containing 3% Americium
|
D’Agata, E.
|
|
2014
|
275 |
C |
p. 300-311
12 p.
|
artikel
|
| 37 |
Stabilization of magnet assemblies of permanent magnet sodium flowmeters used in fast breeder reactors
|
Rajan, K.K.
|
|
2014
|
275 |
C |
p. 368-374
7 p.
|
artikel
|
| 38 |
The importance of input interactions in the uncertainty and sensitivity analysis of nuclear fuel behavior
|
Ikonen, T.
|
|
2014
|
275 |
C |
p. 229-241
13 p.
|
artikel
|
| 39 |
The influence of the mechanical properties on fuel rod support characteristics – A case study of dual cooled fuel
|
Kim, Jae Yong
|
|
2014
|
275 |
C |
p. 53-60
8 p.
|
artikel
|
| 40 |
Thermal transient test and strength evaluation of a tubesheet structure made of Mod.9Cr–1Mo steel. Part II: Creep-fatigue strength evaluation
|
Ando, Masanori
|
|
2014
|
275 |
C |
p. 422-432
11 p.
|
artikel
|
| 41 |
Thermal transient test and strength evaluation of a tubesheet structure made of Mod.9Cr–1Mo steel. Part I: Test model design and experimental results
|
Ando, Masanori
|
|
2014
|
275 |
C |
p. 408-421
14 p.
|
artikel
|
| 42 |
The role of a convective surface in models of the radiative heat transfer in nanofluids
|
Rahman, M.M.
|
|
2014
|
275 |
C |
p. 382-392
11 p.
|
artikel
|
| 43 |
The safety assessment of OPR-1000 nuclear power plant for station blackout accident applying the combined deterministic and probabilistic procedure
|
Kang, Dong Gu
|
|
2014
|
275 |
C |
p. 142-153
12 p.
|
artikel
|
| 44 |
Transient response and radiation dose estimates for breaches to a spent fuel processing facility
|
Solbrig, Charles W.
|
|
2014
|
275 |
C |
p. 352-367
16 p.
|
artikel
|
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