nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Accident safety analysis of flow blockage in an assembly in the JRR-3M research reactor using system code RELAP5 and CFD code FLUENT
|
Guo, Yuchuan |
|
|
122 |
C |
p. 125-136 |
artikel |
2 |
A comprehensive study on source terms in irradiated graphite spheres of HTR-10
|
Xie, Feng |
|
|
122 |
C |
p. 352-365 |
artikel |
3 |
A coupled heat transfer and tritium mass transport model for a double-wall heat exchanger design for FHRs
|
Zhang, Sheng |
|
|
122 |
C |
p. 328-339 |
artikel |
4 |
Analysis of time-dependent failure rate and probability of nuclear component
|
Guo, Haikuan |
|
|
122 |
C |
p. 137-145 |
artikel |
5 |
An innovative method for nuclear emergency source term evaluation based on pressure vessel water level
|
Sun, Xiaohui |
|
|
122 |
C |
p. 309-316 |
artikel |
6 |
A nonlinear model predictive tracking control strategy for modular high-temperature gas-cooled reactors
|
Wang, Guoxu |
|
|
122 |
C |
p. 229-240 |
artikel |
7 |
A small lead-cooled reactor with improved Am-burning and non-proliferation characteristics
|
Wallenius, Janne |
|
|
122 |
C |
p. 193-200 |
artikel |
8 |
A study of the impact of mixed mode of fuel salt in plenum on steady-state performance of channel-type molten salt reactor
|
Zhuang, Kun |
|
|
122 |
C |
p. 207-216 |
artikel |
9 |
Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor
|
Jamil, Zeeshan |
|
|
122 |
C |
p. 155-162 |
artikel |
10 |
Characterization of mixed N/G beam of the VR-1 reactor
|
Košťál, Michal |
|
|
122 |
C |
p. 69-78 |
artikel |
11 |
Cutting performance of thick steel plates up to 150 mm in thickness and large size pipes with a 10-kW fiber laser for dismantling of nuclear facilities
|
Shin, Jae Sung |
|
|
122 |
C |
p. 62-68 |
artikel |
12 |
Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations
|
Blakely, Cole |
|
|
122 |
C |
p. 8-22 |
artikel |
13 |
Development of a method for identifying severe status requiring early entrance of SAMG considering human action time
|
No, Young Gyu |
|
|
122 |
C |
p. 317-327 |
artikel |
14 |
Development of a quantitative resilience model for nuclear power plants
|
Kim, Ji Tae |
|
|
122 |
C |
p. 175-184 |
artikel |
15 |
Development strategy of optimized Level 1&2 PSA model for APR1400 NPPs reflecting new severe accident mitigating system and its application
|
Hwang, Seok-Won |
|
|
122 |
C |
p. 256-269 |
artikel |
16 |
3D whole-core neutron transport simulation using 2D/1D method via multi-level generalized equivalence theory based CMFD acceleration
|
Hao, Chen |
|
|
122 |
C |
p. 79-90 |
artikel |
17 |
Editorial Board
|
|
|
|
122 |
C |
p. ii |
artikel |
18 |
Eigenvalue sensitivity and uncertainty analysis based on a 2-D/1-D whole-core transport code KYADJ
|
Wu, Qu |
|
|
122 |
C |
p. 185-192 |
artikel |
19 |
Framework for fault diagnosis with multi-source sensor nodes in nuclear power plants based on a Bayesian network
|
Wu, Guohua |
|
|
122 |
C |
p. 297-308 |
artikel |
20 |
Improvement of heat-removal capability using heat conduction on a novel reactor cavity cooling system (RCCS) design with passive safety features through radiation and natural convection
|
Takamatsu, Kuniyoshi |
|
|
122 |
C |
p. 201-206 |
artikel |
21 |
Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels
|
Lian, Qiang |
|
|
122 |
C |
p. 241-255 |
artikel |
22 |
Investigation of rotating mode behavior in BWR out-of-phase limit cycle oscillations – Part 1: Reduced order model
|
Wysocki, A. |
|
|
122 |
C |
p. 393-407 |
artikel |
23 |
Investigation of rotating mode behavior in BWR out-of-phase limit cycle oscillations – Part 2: TRACE/PARCS model and physical explanation
|
Wysocki, A. |
|
|
122 |
C |
p. 378-392 |
artikel |
24 |
Monte Carlo method for solving a B 1 equation with complex-valued buckling in asymmetric geometries and generation of directional diffusion coefficients
|
Yamamoto, Toshihiro |
|
|
122 |
C |
p. 37-46 |
artikel |
25 |
Nuclear data uncertainty propagation for spectral reaction ratios
|
Keith, Corey |
|
|
122 |
C |
p. 1-7 |
artikel |
26 |
Numerical investigation on quench of an ex-vessel debris bed at prototypical scale
|
Huang, Zheng |
|
|
122 |
C |
p. 47-61 |
artikel |
27 |
Prediction of the minimum point of the pressure drop in a narrow rectangular channel under a transversely non-uniform heat flux
|
Kim, Taewoo |
|
|
122 |
C |
p. 163-174 |
artikel |
28 |
Review of experimental study on melt pool natural convection behavior
|
Wei, Hongyang |
|
|
122 |
C |
p. 101-117 |
artikel |
29 |
Severe accident management measures for a generic German PWR. Part II: Small-break loss-of-coolant accident
|
Jobst, M. |
|
|
122 |
C |
p. 280-296 |
artikel |
30 |
Severe accident management measures for a generic German PWR. Part I: Station blackout
|
Wilhelm, P. |
|
|
122 |
C |
p. 217-228 |
artikel |
31 |
Simulation of a laboratory-scale experiment for wave propagation and interaction with a structure of undersea topography near a nuclear power plant using a divergence-free SPH
|
Park, So-Hyun |
|
|
122 |
C |
p. 340-351 |
artikel |
32 |
Solving the six-field governing equations for a system code
|
Roth, Glenn A. |
|
|
122 |
C |
p. 366-377 |
artikel |
33 |
Study on structural response of reactor vessel under direct safety injection
|
Weng, Yu |
|
|
122 |
C |
p. 270-279 |
artikel |
34 |
Subchannel void distribution correction model for the two-stage core analysis method in boiling water reactors
|
Mitsuyasu, Takeshi |
|
|
122 |
C |
p. 146-154 |
artikel |
35 |
The packing factor of the pebble bed in molten salt reactor
|
Chen, Xingwei |
|
|
122 |
C |
p. 118-124 |
artikel |
36 |
Th-U breeding performance in a Channel-type molten salt Fast reactor with different starting fuels
|
Yu, Chenggang |
|
|
122 |
C |
p. 91-100 |
artikel |
37 |
Transmission measurements and resonance parameter analysis for Mo-98 and Mo-100
|
Remley, K.E |
|
|
122 |
C |
p. 23-36 |
artikel |