| no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
| 1 |
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems
|
Pelloni, Sandro
|
|
|
163 |
C |
p.
|
article
|
| 2 |
Analysis of radiation emission from MYRRHA spent fuel and implications for non-destructive safeguards verification
|
Preston, M.
|
|
|
163 |
C |
p.
|
article
|
| 3 |
An analytical solution of temperature in a nuclear waste repository
|
Xue, Yao
|
|
|
163 |
C |
p.
|
article
|
| 4 |
An application of sensitivity and representativity approach for the design of a 100%MOX BWR experimental program in ZPR
|
Blaise, Patrick
|
|
|
163 |
C |
p.
|
article
|
| 5 |
A review and analysis of the state of the art on beryllium poisoning in research reactors
|
Wróblewska, Małgorzata
|
|
|
163 |
C |
p.
|
article
|
| 6 |
A review of the development of nuclear fuel performance analysis and codes for PWRs
|
Ding, Ming
|
|
|
163 |
C |
p.
|
article
|
| 7 |
Assessment of PSA Level 2 for core catcher design using a combined probabilistic and deterministic method for a case study: IR-360 NPP
|
Nasiri, Hasti
|
|
|
163 |
C |
p.
|
article
|
| 8 |
A workflow leveraging MOOSE transient multiphysics simulations to evaluate the impact of thermophysical property uncertainties on molten-salt reactors
|
Abou-Jaoude, A.
|
|
|
163 |
C |
p.
|
article
|
| 9 |
Bayesian estimation for covariance between cross-section and errors of experiment and calculation
|
Takeda, Satoshi
|
|
|
163 |
C |
p.
|
article
|
| 10 |
Benchmark tests for the MATXS-formatted XMAP libraries based on ENDF/B-VIII.0 and ENDF/B-VII.1
|
Zhang, Bin
|
|
|
163 |
C |
p.
|
article
|
| 11 |
DEM study of flow characteristics of wet cohesive particles in packed bed
|
Cui, Xiyuan
|
|
|
163 |
C |
p.
|
article
|
| 12 |
Development and application of a Monte Carlo virtual detector—A novel nuclear pulse signal generator
|
Sangang, Li
|
|
|
163 |
C |
p.
|
article
|
| 13 |
Development and verification of a higher-order mathematical adjoint nodal diffusion solver
|
Altahhan, Muhammad Ramzy
|
|
|
163 |
C |
p.
|
article
|
| 14 |
Editorial Board
|
|
|
|
163 |
C |
p.
|
article
|
| 15 |
Equivalence analysis of simulation data and operation data of nuclear power plant based on machine learning
|
Li, Xiangyu
|
|
|
163 |
C |
p.
|
article
|
| 16 |
Experimental study on flow oscillating mechanism of non-condensable gas jet through one- or multi-hole sparger in quiescent water
|
Zhang, D
|
|
|
163 |
C |
p.
|
article
|
| 17 |
Generation of simulated corium using thermite process
|
Hemanth Rao, E.
|
|
|
163 |
C |
p.
|
article
|
| 18 |
Implementation and performance study of the lp-CMFD acceleration scheme for Monte Carlo method based k-eigenvalue neutron transport calculation in 1D geometry
|
Chan, Yimeng
|
|
|
163 |
C |
p.
|
article
|
| 19 |
Improved natural convection heat transfer correlations for reactor cavity cooling systems of high-temperature gas-cooled reactors: From computational fluid dynamics to Pronghorn
|
Freile, Ramiro
|
|
|
163 |
C |
p.
|
article
|
| 20 |
Influence of input data uncertainties on failure probability of TRISO-coated particle
|
Li, Jian
|
|
|
163 |
C |
p.
|
article
|
| 21 |
Infrastructure for the new paradigm of nuclear reaction evaluation
|
Herman, M.
|
|
|
163 |
C |
p.
|
article
|
| 22 |
Introducing optimum parameters of separation cascades for 123Te using GWO based on ANN
|
Imani, Morteza
|
|
|
163 |
C |
p.
|
article
|
| 23 |
Large-scale production by centrifugation of isotopically modified molybdenum for nuclear reactors and its cost evaluation
|
Zeng, S.
|
|
|
163 |
C |
p.
|
article
|
| 24 |
Microstructure and mechanical properties of the LWR solidified melt prototype obtained by the out-of-pile experiment
|
Mukhamedov, N.Ye.
|
|
|
163 |
C |
p.
|
article
|
| 25 |
Multiphysics analysis of thorium-based fuel performance with a two-layer SiC cladding under normal operating and transient conditions in a light water reactor
|
Qiu, Chenjie
|
|
|
163 |
C |
p.
|
article
|
| 26 |
Neutronic analysis of the ALLEGRO fast reactor core with deterministic ERANOS code and Monte Carlo Serpent code
|
Lima Reinaldo, Yrobel
|
|
|
163 |
C |
p.
|
article
|
| 27 |
Nodal integral method for 3D time-dependent anisotropic convection-diffusion equation
|
Jarrah, Ibrahim
|
|
|
163 |
C |
p.
|
article
|
| 28 |
Nuclear data evaluation augmented by machine learning
|
Vicente-Valdez, Pedro
|
|
|
163 |
C |
p.
|
article
|
| 29 |
Numerical analysis for FP speciation in VERDON-2 experiment: Chemical re-vaporization of iodine in air ingress condition
|
Shiotsu, Hiroyuki
|
|
|
163 |
C |
p.
|
article
|
| 30 |
Numerical investigation of thermal hydraulic behaviors in wire-wrapped bundle with smaller wire diameter of peripheral rods
|
Lyu, Kefeng
|
|
|
163 |
C |
p.
|
article
|
| 31 |
On some features of the eigenvalue problem for the P N approximation of the neutron transport equation
|
Abrate, Nicolò
|
|
|
163 |
C |
p.
|
article
|
| 32 |
Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part II: Methodology application
|
Di Nora, V.A.
|
|
|
163 |
C |
p.
|
article
|
| 33 |
Overview on critical heat flux experiment for the reactor fuel assemblies
|
Lu, Donghua
|
|
|
163 |
C |
p.
|
article
|
| 34 |
Phase distribution of uranium in matrices obtained by co-melting basalt and uranium-containing aluminum oxide
|
Martynov, K.V.
|
|
|
163 |
C |
p.
|
article
|
| 35 |
Preliminary analysis on the thermal-mechanical behavior of dispersed plate-type fuel under reactivity insertion accident
|
Wang, Yangyang
|
|
|
163 |
C |
p.
|
article
|
| 36 |
Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor
|
Alameri, Saeed A.
|
|
|
163 |
C |
p.
|
article
|
| 37 |
Progress on the reevaluation and validation of the n+233U neutron cross sections
|
Pigni, Marco T.
|
|
|
163 |
C |
p.
|
article
|
| 38 |
Research on scaling analysis and design parameters of integral test facilities for PWR
|
Li, Liangguo
|
|
|
163 |
C |
p.
|
article
|
| 39 |
Semi wavelet-based improved quasi static method for the analysis of PHWR transients
|
Mohideen Abdul Razak, M.
|
|
|
163 |
C |
p.
|
article
|
| 40 |
Stability analysis of a parallel channel-loop system with single-phase natural circulation under asymmetric conditions
|
Zhu, Enping
|
|
|
163 |
C |
p.
|
article
|
| 41 |
Study on adaptive heat transfer performance of high temperature heat pipe
|
Ji, Yang
|
|
|
163 |
C |
p.
|
article
|
| 42 |
The effect of oblique crack on stability and fracture properties of Cr-coated Zircaloy cladding
|
Xu, Ze
|
|
|
163 |
C |
p.
|
article
|
| 43 |
Thorough analyses and resolution of various errors in pin-homogenized multigroup core calculation
|
Hong, Hyunsik
|
|
|
163 |
C |
p.
|
article
|
| 44 |
Turbulent flow effect on integrity of pressurized RVIs
|
Je, Sang Yun
|
|
|
163 |
C |
p.
|
article
|
| 45 |
Uncertainty propagation from n+56Fe nuclear reaction model parameters to neutron multiplication factor
|
Chen, Shengli
|
|
|
163 |
C |
p.
|
article
|
| 46 |
Validation of Monte Carlo activation calculation for V1 NPP reactor concrete shaft
|
Šnírer, Michal
|
|
|
163 |
C |
p.
|
article
|
Journal description