Results 31 to 40 of about 3,602,304 (354)

Modeling and simulation of a High Flux Isotope Reactor representative core model for updated performance and safety basis assessments

, 2020
A high-fidelity neutronics model of the Oak Ridge National Laboratory High Flux Isotope Reactor (HFIR) with a representative core and experiment loading was developed to serve as the new basis for performance and safety basis assessments.
D. Chandler, B. Betzler, E. Davidson, G. Ilas   +3 more
semanticscholar   +1 more source

Perspectives on reactor safety [PDF]

, 1994
The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident
Haskin, F. E., Camp, A. L.
openaire   +2 more sources

Amyloid adhesin production in activated sludge is enhanced in lab-scale sequencing batch reactors: Feeding regime impacts microbial community and amyloid distribution

Water Research X, 2022
Amyloid adhesins are β-sheet-rich extracellular proteins thought to contribute to bioflocculation. They are present in activated sludge to varying extent. However, it remains unclear which operational conditions promote their production. To this end, the
An-Sofie Christiaens, Manon Van Steenkiste, Koen Rummens, Ilse Smets   +3 more
doaj   +1 more source

Generalized Reich-Moore R-matrix approximation

EPJ Web of Conferences, 2017
A conventional Reich-Moore approximation (RMA) of R-matrix is generalized into a manifestly unitary form by introducing a set of resonant capture channels treated explicitly in a generalized, reduced R-matrix.
Arbanas Goran, Sobes Vladimir, Holcomb Andrew, Ducru Pablo, Pigni Marco, Wiarda Dorothea   +5 more
doaj   +1 more source

An Experimental Analysis on Nusselt Number of Natural Circulation Flow in Transient Condition Based on the Height Differences between Heater and Cooler

Atom Indonesia, 2018
A better understanding on the phenomenon of natural circulation flow for cooling systems is necessary prior to improving the safety of nuclear power plant, not only in normal operation but also in accident conditions.
M. Juarsa, J.P. Witoko, G Giarno, D. Haryanto, J.H. Purba   +4 more
doaj   +1 more source

Development of phenomena identification and ranking table for Westinghouse lead fast reactor's safety

, 2020
The Westinghouse Lead-cooled Fast Reactor (LFR) is a medium-size, passively safe, economic, Gen-IV nuclear reactor. An important effort within the Westinghouse LFR program is the development of the safety analysis methodology, which comprises computer ...
J. Liao, P. Ferroni, R. Wright, Uriel Bachrach, J. Scobel, T. Sofu, A. Tentner, S. Lee, M. Epstein, M. Frignani, M. Tarantino   +10 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

Approximate model for evaluation of thermal-hydraulic transients associated with rapid power increase in research nuclear reactor [PDF]

Nuclear Technology and Radiation Protection, 2020
A simple model, for the estimation of changes in the nuclear fuel element cladding temperature as well as the conditions of the formation of the onset of nucleate boiling, is proposed.
Lipka Maciej, Madejowski Gawel, Prokopowicz Rafal, Pytelt Krzysztof   +3 more
doaj   +1 more source

Physics-informed neural network with transfer learning (TL-PINN) based on domain similarity measure for prediction of nuclear reactor transients

Scientific Reports, 2023
Nuclear reactor safety and efficiency can be enhanced through the development of accurate and fast methods for prediction of reactor transient (RT) states.
Konstantinos Prantikos, S. Chatzidakis, L. Tsoukalas, Alexander Heifetz   +3 more
semanticscholar   +1 more source

Microstructural Evolution and Vacancy Defect Formation in Mn–Mo–Ni RPV Steel Under Low Cycle Fatigue: Insights From EBSD and PALS

Advanced Engineering Materials, EarlyView.
Low‐cycle fatigue damage in Mn–Mo–Ni reactor pressure vessel steel is examined using a combined electron backscatter diffraction and positron annihilation lifetime spectroscopy approach. The study correlates texture evolution, dislocation substructure development, and vacancy‐type defect formation across uniform, necked, and fracture regions, providing
Apu Sarkar, Dhanadeep Dutta, G. Bharat Reddy   +2 more
wiley   +1 more source