A New Method to Efficiently Estimate the Equilibrium State of Pebble Bed Reactors

Kairos power thermal hydraulics research and development

(2020) Edward Blandford et al.   NUCLEAR ENGINEERING AND DESIGN

Analysis of the pebble burnup profile in a pebble-bed nuclear reactor

(2019) Yushi Tang et al.   NUCLEAR ENGINEERING AND DESIGN

Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost

(2019) Cihang Lu et al.   NUCLEAR ENGINEERING AND DESIGN

Neutronics characteristics of a 165 MWth Xe-100 reactor

(2019) E.J. Mulder et al.   NUCLEAR ENGINEERING AND DESIGN

Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics

(2018) Cihang Lu et al.   ANNALS OF NUCLEAR ENERGY

Corrosion of Incoloy 800H alloys with nickel cladding in FLiNaK salts at 850 °C

(2018) Qilong Dai et al.   CORROSION SCIENCE

The enhanced fuel management models of the HTR code package (HCP) module SHUFLE

(2018) A. Xhonneux et al.   NUCLEAR ENGINEERING AND DESIGN

PANGU code for pebble-bed HTGR reactor physics and fuel cycle simulations

(2018) Ding She et al.   ANNALS OF NUCLEAR ENERGY

Neutronics and Safety Studies on a Research Reactor Concept for an Advanced Neutron Source

(2017) Zeyun Wu et al.   NUCLEAR TECHNOLOGY

A Core Design Study for a Small Modular Boiling Water Reactor with Long-Life Core

(2016) Zeyun Wu et al.   NUCLEAR TECHNOLOGY

The Serpent Monte Carlo code: Status, development and applications in 2013

(2015) Jaakko Leppänen et al.   ANNALS OF NUCLEAR ENERGY

Equilibrium Core Composition Search Methodologies for Pebble Bed Reactors

(2015) Massimiliano Fratoni et al.   NUCLEAR SCIENCE AND ENGINEERING

Development of Monte Carlo-based pebble bed reactor fuel management code

(2014) Topan Setiadipura et al.   ANNALS OF NUCLEAR ENERGY

Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices

(2010) E. Bomboni et al.   NUCLEAR ENGINEERING AND DESIGN

Thermohydraulic transient studies of the Chinese 200MWe HTR-PM for loss of forced cooling accidents

(2009) Yanhua Zheng et al.   ANNALS OF NUCLEAR ENERGY