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Research article

First published 2018-12

The application of supercritical CO 2 in nuclear engineering: A review

Houbo Qi, Nan Gui, Xingtuan Yang [...]

The Journal of Computational Multiphase Flows

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Research article

First published 2014-8

Pressurized water reactor core thermal-hydraulics model for flow coastdown transient

I Ahmad, M Ilyas, Z Akram

Proceedings of the Institution of Mechanical Engineers,Part A: Journal of Power and Energy

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Research article

First published 2019-3

Reliability analysis of the precision assembly process of a scaled stator can of the AP1000 reactor coolant pump

Wei Jiang, Huahan Liu

Proceedings of the Institution of Mechanical Engineers,Part C: Journal of Mechanical Engineering Science

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Research article

First published 2018-6

An improved core thermal-hydraulic model for coastdown transient in pressurized water reactor

Idrees Ahmad, Saad Arshad, Sajjad Tahir [...]

Proceedings of the Institution of Mechanical Engineers,Part A: Journal of Power and Energy

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Other

First published 1954-6

Nuclear Reactors and Power Production *

Christopher Hinton

Proceedings of the Institution of Mechanical Engineers

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Research article

First published 2014-5

Converting energy from fusion into useful forms

M Kovari, C Harrington, I Jenkins [...]

Proceedings of the Institution of Mechanical Engineers,Part A: Journal of Power and Energy

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Research article

First published 2015-2

Lumped parameter method application in nuclear engineering – AP1000 DVI line break accident analysis by RELAP5

Xue-Dong Qiao, Jian-Ping Jing, Jie-Ru An [...]

Journal of Computational Methods in Sciences and Engineering

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Other

First published 1969-9

Velocity of Sound and Critical Discharge Pressure in Annular Two-Phase Flow

R. F. White, D. F. D'Arcy

Proceedings of the Institution of Mechanical Engineers,Conference Proceedings

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Research article

First published 1980-07

Hybrid simulation of reactor kinetics in CANDU reactors using a modal approach

Brian M. Monaghan, Frank N. McDonnell, H.W. Hinds

SIMULATION

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Research article

First published 1968-9

Paper 1: Dragon Reactor Fuel-Handling Equipment

A. N. Kinkead, P. C. Smith

Proceedings of the Institution of Mechanical Engineers,Conference Proceedings

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