Nuclear Engineering and Design

Small punch test method assessment for the determination of the residual creep life of service exposed components: outcomes from an interlaboratory exercise
pp. 1-11(11)
Authors: Ule B.; Sustar T.; Dobes F.; Milicka K.; Bicego V.; Tettamanti S.; Maile K.; Schwarzkopf C.; Whelan M.P.; Kozlowski R.H.; Klaput J.

Prediction of air and steam leak rate through cracked reinforced concrete panels
pp. 13-30(18)
Authors: Riva P.; Brusa L.; Contri P.; Imperato L.

Dynamics of multiple parallel boiling channel systems with forced flows
pp. 31-44(14)
Authors: Lee J.D.; Pan C.

Flooding in the pressurizer surge line of AP600 plant and analyses of APEX data
pp. 45-58(14)
Authors: Takeuchi K.; Young M.Y.; Gagnon A.F.

Gas-liquid two-phase flow in narrow horizontal annuli
pp. 59-80(22)
Authors: Ekberg N.P.; Ghiaasiaan S.M.; Abdel-Khalik S.I.; Yoda M.; Jeter S.M.

Mechanical analysis of fuel fretting problem
pp. 81-93(13)
Author: Kim H.-K.

Inspection and testing of unfired pressure vessels
pp. 95-102(8)
Authors: Baylac G.; Larabi M.

Intelligent system for transient data collection and fatigue monitoring of pressurised water reactors nuclear steam supply system
pp. 103-109(7)
Authors: Morilhat P.; Chau T.H.; Savoldelli D.; Mallez C.