| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Advanced Bondarenko method for resonance self-shielding calculations in deterministic reactor physics code system CBZ
|
Chiba, Go
|
|
2016
|
96 |
C |
p. 277-286
|
artikel
|
| 2 |
Advanced CANDU reactors axial xenon oscillation controllability validation
|
Chang, G.S.
|
|
2016
|
96 |
C |
p. 441-445
|
artikel
|
| 3 |
Analyses of UTOP events for the design of control rod stop system in PGSFR using MARS-LMR
|
Choi, Chiwoong
|
|
2016
|
96 |
C |
p. 422-431
|
artikel
|
| 4 |
Analysis of experimental series of plutonium nitrate in aqueous solution and their correlation coefficients
|
Kilger, Robert
|
|
2016
|
96 |
C |
p. 354-362
|
artikel
|
| 5 |
A new and rigorous SPN theory for piecewise homogeneous regions
|
Chao, Yung-An
|
|
2016
|
96 |
C |
p. 112-125
|
artikel
|
| 6 |
Applying image analysis techniques to tomographic images of irradiated nuclear fuel assemblies
|
Davour, Anna
|
|
2016
|
96 |
C |
p. 223-229
|
artikel
|
| 7 |
A study for Unsafe Act classification under crew interaction during procedure-driven operation
|
Choi, Sun Yeong
|
|
2016
|
96 |
C |
p. 187-196
|
artikel
|
| 8 |
Benchmarking of 232Th evaluation by a 14.8MeV neutron leakage spectra experiment with slab samples
|
Lin, Zuokang
|
|
2016
|
96 |
C |
p. 181-186
|
artikel
|
| 9 |
Comparison of reactivity estimation performance between two extended Kalman filtering schemes
|
Peng, Xingjie
|
|
2016
|
96 |
C |
p. 76-82
|
artikel
|
| 10 |
Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor
|
Shchurovskaya, M.V.
|
|
2016
|
96 |
C |
p. 332-343
|
artikel
|
| 11 |
Coupled MCNP6/CTF code: Development, testing, and application
|
Bennett, A.
|
|
2016
|
96 |
C |
p. 1-11
|
artikel
|
| 12 |
Designing a heterogeneous subcritical nuclear reactor with thorium-based fuel
|
Medina-Castro, Diego
|
|
2016
|
96 |
C |
p. 455-458
|
artikel
|
| 13 |
Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform
|
Fiorina, Carlo
|
|
2016
|
96 |
C |
p. 212-222
|
artikel
|
| 14 |
Development of a fuel depletion sensitivity calculation module for multi-cell problems in a deterministic reactor physics code system CBZ
|
Chiba, Go
|
|
2016
|
96 |
C |
p. 313-323
|
artikel
|
| 15 |
Editorial board
|
|
|
2016
|
96 |
C |
p. IFC
|
artikel
|
| 16 |
Effect of the time variation of the neutron current density in the calculation of the reactivity
|
Palma, Daniel A.P.
|
|
2016
|
96 |
C |
p. 204-211
|
artikel
|
| 17 |
Enhanced finite difference scheme for the neutron diffusion equation using the importance function
|
Vagheian, Mehran
|
|
2016
|
96 |
C |
p. 412-421
|
artikel
|
| 18 |
Enhancing plutonium incineration in the thorium-based I2S-LWR design with loading pattern optimization
|
Kotlyar, Dan
|
|
2016
|
96 |
C |
p. 401-411
|
artikel
|
| 19 |
Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor
|
Vela-García, M.
|
|
2016
|
96 |
C |
p. 446-454
|
artikel
|
| 20 |
Exergy analysis of thermal energy storage options with nuclear power plants
|
Edwards, Jacob
|
|
2016
|
96 |
C |
p. 104-111
|
artikel
|
| 21 |
Flux renormalization in constant power burnup calculations
|
Isotalo, A.E.
|
|
2016
|
96 |
C |
p. 148-157
|
artikel
|
| 22 |
Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia
|
Chiesa, Davide
|
|
2016
|
96 |
C |
p. 270-276
|
artikel
|
| 23 |
Gamma-ray mass attenuation coefficient and half value layer factor of some oxide glass shielding materials
|
Waly, El-Sayed A.
|
|
2016
|
96 |
C |
p. 26-30
|
artikel
|
| 24 |
Heuristic optimization of group structure using Physics-Based Fitness Approximation
|
Yi, C.
|
|
2016
|
96 |
C |
p. 389-400
|
artikel
|
| 25 |
Hydrodynamic cavitation characteristics of an orifice system and its effects on CRUD-like SiC deposition
|
Kim, Seong Man
|
|
2016
|
96 |
C |
p. 12-18
|
artikel
|
| 26 |
Identification of fuel cycle simulator functionalities for analysis of transition to a new fuel cycle
|
Brown, Nicholas R.
|
|
2016
|
96 |
C |
p. 88-95
|
artikel
|
| 27 |
Inverse uncertainty quantification of trace physical model parameters using BFBT benchmark data
|
Hu, Guojun
|
|
2016
|
96 |
C |
p. 197-203
|
artikel
|
| 28 |
Maintaining a critical spectra within Monteburns for a gas-cooled reactor array by way of control rod manipulation
|
Adigun, Babatunde J.
|
|
2016
|
96 |
C |
p. 36-60
|
artikel
|
| 29 |
Memory-efficient calculations of adjoint-weighted tallies by the Monte Carlo Wielandt method
|
Choi, Sung Hoon
|
|
2016
|
96 |
C |
p. 287-294
|
artikel
|
| 30 |
Microstructural evolution of reactor internals stainless steel under xenon irradiation studied by GIXRD and positron annihilation technique
|
Xu, Chaoliang
|
|
2016
|
96 |
C |
p. 176-180
|
artikel
|
| 31 |
MOCUM solutions and sensitivity study for C5G7 benchmark
|
Yang, Xue
|
|
2016
|
96 |
C |
p. 242-248
|
artikel
|
| 32 |
Monte Carlo analysis of the CROCUS benchmark on kinetics parameters calculation
|
Zoia, Andrea
|
|
2016
|
96 |
C |
p. 377-388
|
artikel
|
| 33 |
Neutronics and thermal hydraulics analysis of a low-enriched uranium cermet fuel core for a Mars surface power reactor
|
Schillo, Kevin J.
|
|
2016
|
96 |
C |
p. 307-312
|
artikel
|
| 34 |
New reactor cavity cooling system (RCCS) with passive safety features: A comparative methodology between a real RCCS and a scaled-down heat-removal test facility
|
Takamatsu, Kuniyoshi
|
|
2016
|
96 |
C |
p. 137-147
|
artikel
|
| 35 |
Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code
|
Leppänen, Jaakko
|
|
2016
|
96 |
C |
p. 126-136
|
artikel
|
| 36 |
Performance of Estimation of distribution algorithm for initial core loading optimization of AHWR-LEU
|
Thakur, Amit
|
|
2016
|
96 |
C |
p. 230-241
|
artikel
|
| 37 |
Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core
|
Zheng, M.Y.
|
|
2016
|
96 |
C |
p. 363-376
|
artikel
|
| 38 |
Real-time implementation of a stability monitor for BWRs
|
Laguna-Sanchez, Gerardo
|
|
2016
|
96 |
C |
p. 83-87
|
artikel
|
| 39 |
Relativistic kinematics for photoneutron production in Monte Carlo transport calculations
|
Caro, Edmund
|
|
2016
|
96 |
C |
p. 170-175
|
artikel
|
| 40 |
Selecting benchmarks for reactor simulations: An application to a lead fast reactor
|
Alhassan, E.
|
|
2016
|
96 |
C |
p. 158-169
|
artikel
|
| 41 |
Source term in the linear analysis of FNPK equations
|
Espinosa-Paredes, Gilberto
|
|
2016
|
96 |
C |
p. 432-440
|
artikel
|
| 42 |
Stability in boiling water reactor using fuel assemblies containing inert matrix as a fuel reload option
|
Rogelio, Castillo-Duran
|
|
2016
|
96 |
C |
p. 31-35
|
artikel
|
| 43 |
Stored energy analysis in the scaled-down test facilities
|
Deng, Chengcheng
|
|
2016
|
96 |
C |
p. 19-25
|
artikel
|
| 44 |
Study on the Doppler reactivity worth considering thermal agitation in epithermal range for various types of nuclear fuels
|
Takeda, Satoshi
|
|
2016
|
96 |
C |
p. 264-269
|
artikel
|
| 45 |
Sub-step methodology for coupled Monte Carlo depletion and thermal hydraulic codes
|
Kotlyar, D.
|
|
2016
|
96 |
C |
p. 61-75
|
artikel
|
| 46 |
Temperature dependent subgroup formulation with number density adjustment for direct whole core power reactor calculation
|
Jung, Yeon Sang
|
|
2016
|
96 |
C |
p. 249-263
|
artikel
|
| 47 |
Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark – HFP conditions and fuel cycle 1 simulations
|
Leppänen, Jaakko
|
|
2016
|
96 |
C |
p. 324-331
|
artikel
|
| 48 |
Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K
|
Dokhane, A.
|
|
2016
|
96 |
C |
p. 344-353
|
artikel
|
| 49 |
Verification of MCNP6 model of the Jordan Research and Training Reactor (JRTR) for calculations of neutronic parameters
|
Jaradat, Mustafa K.
|
|
2016
|
96 |
C |
p. 96-103
|
artikel
|
| 50 |
XGPT: Extending Monte Carlo Generalized Perturbation Theory capabilities to continuous-energy sensitivity functions
|
Aufiero, Manuele
|
|
2016
|
96 |
C |
p. 295-306
|
artikel
|
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