Results 1 to 10 of about 25,910 (172)

The Chicago Piles unearthed [PDF]

Scientific Reports
The divergence of the Chicago Pile 1 (CP-1) on December 2nd, 1942 marks the birth of the nuclear age. CP-1 was the first nuclear reactor, conceived as a proof-of-principle physics experiment to demonstrate the feasibility of a self-sustained neutron ...
Andrea Zoia, Albin Gagnepain, Davide Mancusi   +2 more
doaj   +2 more sources

Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation

Nuclear Engineering and Technology, 2021
The aim of this work considers a second order point reactor kinetics model based on the P1 approximation of transport theory, called in this work as P1 point reactor model.
Daniel Suescún-Díaz, Gilberto Espinosa-Paredes, Freddy Humberto Escobar   +2 more
doaj   +2 more sources

VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS [PDF]

EPJ Web of Conferences, 2021
The WIMS (Winfrith Improved Multigroup Scheme) reactor physics code is actively being developed for whole core modelling of a range of Small Modular Reactor types including the Pressurized Water Reactor (PWR), High Temperature Reactor (HTR), and Liquid ...
Smith Peter, Hosking Glynn, Tollit Brendan, Lindley Ben, Cox Andrew, Perry Ray, Ware Tim, Mason Robert, Stefanowska Magda   +8 more
doaj   +1 more source

Nuclear data sensitivity analysis and uncertainty propagation in the KYADJ whole-core transport code [PDF]

EPJ Web of Conferences, 2020
Nuclear data sensitivity analysis and uncertainty propagation have been extensively applied to nuclear data adjustment and uncertainty quantification in the field of nuclear engineering.
Wu Qu, Peng Xingjie, Shi Guanlin, Yu Yingrui, Li Qing, Wang Kan   +5 more
doaj   +1 more source

Simulation of the burnup in cell calculation using the wimsd-5b code considering different nuclear data libraries

Brazilian Journal of Radiation Sciences, 2021
This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose
Desirée Yael de Sena Tavares, Adilson Costa da Silva, Zelmo Rodrigues de Lima   +2 more
doaj   +1 more source

Percolation properties of the neutron population in nuclear reactors. [PDF]

Physical Review E, 2022
Reactor physics aims at studying the neutron population in a reactor core under the influence of feedback mechanisms, such as the Doppler temperature effect.
B. Dechenaux, Thomas Delcambre, Eric Dumonteil   +2 more
semanticscholar   +1 more source

The steady-state neutronic analysis and transient simulation of ADANES reactor design based on deterministic method

He jishu, 2022
BackgroundAt present, in the key stage of the construction of China Initiative Accelerator Driven System, various research institutes have also put forward corresponding core schemes for different purposes, including the accelerators drive advanced ...
DU Xianan, WANG Yongping, ZHENG Youqi, CAO Liangzhi, ZHANG Yanshi, YAN Xuesong, YANG Lei   +6 more
doaj   +1 more source

Generalized Perturbation Theory Based Total Sensitivity and Uncertainty Analysis for High-Fidelity Neutronics Calculation

Frontiers in Energy Research, 2021
Neutronics calculation for nuclear reactor with high-fidelity technology can significantly reduce the uncertainties propagated from numerical approximation error and model error.
Ji Ma, Chen Hao, Guanghao Liu, Le Kang, Peijun Li, Florencia de los Angeles Renteria del Toro   +5 more
doaj   +1 more source

Multischeme equivalence procedure for neutron transport finite element methods

Annals of Nuclear Energy, 2022
Diffusion equivalence theory applied at the full-core level is well understood and enables preservation of the multiplication factor and key reaction rates.
V. Labouré, Yaqi Wang, J. Ortensi, N. Martin, S. Schunert   +4 more
semanticscholar   +1 more source

STUDY ON MCNP6 MODEL IN THE CALCULATION OF KINETIC PARAMETERS FOR PEBBLE BED REACTOR

Acta Polytechnica, 2020
When conducting a nuclear reactor transient analysis, the most important parameter, called the kinetic parameter, is required. The calculation of kinetic parameters can be conducted using several methods.
Zuhair, Suwoto, Topan Setiadipura, Zaki Su'ud   +3 more
doaj   +1 more source