| no |
title |
author |
magazine |
year |
volume |
issue |
page(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
|
article
|
| 2 |
A comprehensive study on source terms in irradiated graphite spheres of HTR-10
|
Xie, Feng
|
|
|
122 |
C |
p. 352-365
|
article
|
| 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
|
article
|
| 4 |
Analysis of time-dependent failure rate and probability of nuclear component
|
Guo, Haikuan
|
|
|
122 |
C |
p. 137-145
|
article
|
| 5 |
An innovative method for nuclear emergency source term evaluation based on pressure vessel water level
|
Sun, Xiaohui
|
|
|
122 |
C |
p. 309-316
|
article
|
| 6 |
A nonlinear model predictive tracking control strategy for modular high-temperature gas-cooled reactors
|
Wang, Guoxu
|
|
|
122 |
C |
p. 229-240
|
article
|
| 7 |
A small lead-cooled reactor with improved Am-burning and non-proliferation characteristics
|
Wallenius, Janne
|
|
|
122 |
C |
p. 193-200
|
article
|
| 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
|
article
|
| 9 |
Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor
|
Jamil, Zeeshan
|
|
|
122 |
C |
p. 155-162
|
article
|
| 10 |
Characterization of mixed N/G beam of the VR-1 reactor
|
Košťál, Michal
|
|
|
122 |
C |
p. 69-78
|
article
|
| 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
|
article
|
| 12 |
Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations
|
Blakely, Cole
|
|
|
122 |
C |
p. 8-22
|
article
|
| 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
|
article
|
| 14 |
Development of a quantitative resilience model for nuclear power plants
|
Kim, Ji Tae
|
|
|
122 |
C |
p. 175-184
|
article
|
| 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
|
article
|
| 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
|
article
|
| 17 |
Editorial Board
|
|
|
|
122 |
C |
p. ii
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 21 |
Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels
|
Lian, Qiang
|
|
|
122 |
C |
p. 241-255
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 25 |
Nuclear data uncertainty propagation for spectral reaction ratios
|
Keith, Corey
|
|
|
122 |
C |
p. 1-7
|
article
|
| 26 |
Numerical investigation on quench of an ex-vessel debris bed at prototypical scale
|
Huang, Zheng
|
|
|
122 |
C |
p. 47-61
|
article
|
| 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
|
article
|
| 28 |
Review of experimental study on melt pool natural convection behavior
|
Wei, Hongyang
|
|
|
122 |
C |
p. 101-117
|
article
|
| 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
|
article
|
| 30 |
Severe accident management measures for a generic German PWR. Part I: Station blackout
|
Wilhelm, P.
|
|
|
122 |
C |
p. 217-228
|
article
|
| 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
|
article
|
| 32 |
Solving the six-field governing equations for a system code
|
Roth, Glenn A.
|
|
|
122 |
C |
p. 366-377
|
article
|
| 33 |
Study on structural response of reactor vessel under direct safety injection
|
Weng, Yu
|
|
|
122 |
C |
p. 270-279
|
article
|
| 34 |
Subchannel void distribution correction model for the two-stage core analysis method in boiling water reactors
|
Mitsuyasu, Takeshi
|
|
|
122 |
C |
p. 146-154
|
article
|
| 35 |
The packing factor of the pebble bed in molten salt reactor
|
Chen, Xingwei
|
|
|
122 |
C |
p. 118-124
|
article
|
| 36 |
Th-U breeding performance in a Channel-type molten salt Fast reactor with different starting fuels
|
Yu, Chenggang
|
|
|
122 |
C |
p. 91-100
|
article
|
| 37 |
Transmission measurements and resonance parameter analysis for Mo-98 and Mo-100
|
Remley, K.E
|
|
|
122 |
C |
p. 23-36
|
article
|
Journal description