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no title author magazine year volume issue page(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
 article
2 Advanced CANDU reactors axial xenon oscillation controllability validation Chang, G.S.
 2016
 96 C p. 441-445
 article
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
 article
4 Analysis of experimental series of plutonium nitrate in aqueous solution and their correlation coefficients Kilger, Robert
 2016
 96 C p. 354-362
 article
5 A new and rigorous SPN theory for piecewise homogeneous regions Chao, Yung-An
 2016
 96 C p. 112-125
 article
6 Applying image analysis techniques to tomographic images of irradiated nuclear fuel assemblies Davour, Anna
 2016
 96 C p. 223-229
 article
7 A study for Unsafe Act classification under crew interaction during procedure-driven operation Choi, Sun Yeong
 2016
 96 C p. 187-196
 article
8 Benchmarking of 232Th evaluation by a 14.8MeV neutron leakage spectra experiment with slab samples Lin, Zuokang
 2016
 96 C p. 181-186
 article
9 Comparison of reactivity estimation performance between two extended Kalman filtering schemes Peng, Xingjie
 2016
 96 C p. 76-82
 article
10 Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor Shchurovskaya, M.V.
 2016
 96 C p. 332-343
 article
11 Coupled MCNP6/CTF code: Development, testing, and application Bennett, A.
 2016
 96 C p. 1-11
 article
12 Designing a heterogeneous subcritical nuclear reactor with thorium-based fuel Medina-Castro, Diego
 2016
 96 C p. 455-458
 article
13 Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform Fiorina, Carlo
 2016
 96 C p. 212-222
 article
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
 article
15 Editorial board 2016
 96 C p. IFC
 article
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
 article
17 Enhanced finite difference scheme for the neutron diffusion equation using the importance function Vagheian, Mehran
 2016
 96 C p. 412-421
 article
18 Enhancing plutonium incineration in the thorium-based I2S-LWR design with loading pattern optimization Kotlyar, Dan
 2016
 96 C p. 401-411
 article
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
 article
20 Exergy analysis of thermal energy storage options with nuclear power plants Edwards, Jacob
 2016
 96 C p. 104-111
 article
21 Flux renormalization in constant power burnup calculations Isotalo, A.E.
 2016
 96 C p. 148-157
 article
22 Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia Chiesa, Davide
 2016
 96 C p. 270-276
 article
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
 article
24 Heuristic optimization of group structure using Physics-Based Fitness Approximation Yi, C.
 2016
 96 C p. 389-400
 article
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
 article
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
 article
27 Inverse uncertainty quantification of trace physical model parameters using BFBT benchmark data Hu, Guojun
 2016
 96 C p. 197-203
 article
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
 article
29 Memory-efficient calculations of adjoint-weighted tallies by the Monte Carlo Wielandt method Choi, Sung Hoon
 2016
 96 C p. 287-294
 article
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
 article
31 MOCUM solutions and sensitivity study for C5G7 benchmark Yang, Xue
 2016
 96 C p. 242-248
 article
32 Monte Carlo analysis of the CROCUS benchmark on kinetics parameters calculation Zoia, Andrea
 2016
 96 C p. 377-388
 article
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
 article
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
 article
35 Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code Leppänen, Jaakko
 2016
 96 C p. 126-136
 article
36 Performance of Estimation of distribution algorithm for initial core loading optimization of AHWR-LEU Thakur, Amit
 2016
 96 C p. 230-241
 article
37 Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core Zheng, M.Y.
 2016
 96 C p. 363-376
 article
38 Real-time implementation of a stability monitor for BWRs Laguna-Sanchez, Gerardo
 2016
 96 C p. 83-87
 article
39 Relativistic kinematics for photoneutron production in Monte Carlo transport calculations Caro, Edmund
 2016
 96 C p. 170-175
 article
40 Selecting benchmarks for reactor simulations: An application to a lead fast reactor Alhassan, E.
 2016
 96 C p. 158-169
 article
41 Source term in the linear analysis of FNPK equations Espinosa-Paredes, Gilberto
 2016
 96 C p. 432-440
 article
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
 article
43 Stored energy analysis in the scaled-down test facilities Deng, Chengcheng
 2016
 96 C p. 19-25
 article
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
 article
45 Sub-step methodology for coupled Monte Carlo depletion and thermal hydraulic codes Kotlyar, D.
 2016
 96 C p. 61-75
 article
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
 article
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
 article
48 Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K Dokhane, A.
 2016
 96 C p. 344-353
 article
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
 article
50 XGPT: Extending Monte Carlo Generalized Perturbation Theory capabilities to continuous-energy sensitivity functions Aufiero, Manuele
 2016
 96 C p. 295-306
 article
                             50 results found
 
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