Volume 119; Issue 2-3

Main
Nuclear Engineering and Design
Volume 119; Issue 2-3

Nuclear Engineering and Design

Volume 119; Issue 2-3

1

Preface

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 168 KB

english, 1990

2

A review of the UK PWR structural integrity and materials programme

B.J. Darlaston, W.E. Gardner

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 697 KB

english, 1990

3

Load carrying behaviour of the primary system of PWRs for loads beyond the design limits: Part 2: Creep and failure behaviour of a piping section under internal pressure and high temperature

K. Maile, A. Klenk, V. Obst, D. Sturm

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 661 KB

english, 1990

4

The effect of chemical composition on irradiation embrittlement

S. Ishino, T. Kawakami, T. Hidaka, M. Satoh

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 530 KB

english, 1990

5

Material laws for inelastic analyses on elbows of 12% or 0.5% Cr-steel up to creep rupture for 30 000 hours creep tests at 550°C

H. Kastl, M. Naraghi

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 2.13 MB

english, 1990

6

Study on 214Cr−1 mo steel for high temperature gas-cooled reactor material characterization of forged low Si 214Cr-1 mo steel

T. Oku, T. Kodaira, K. Fukaya, M. Suzuki, Y. Tanaka, T. Iwadate, K. Suzuki, I. Sato

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 626 KB

english, 1990

7

Evaluation of design values for strain limitation on the basis of cyclic fatigue data

D. Blind, V. Obst, K. Maile, K.J. Kessler, G. Vazoukis

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 468 KB

english, 1990

8

Alloy 800: new stress rupture and creep data for pressurized components in high temperature reactors

Hermann Diehl, Erik Bodmann

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 885 KB

english, 1990

9

Alloy 800: low cycle fatigue curves as the basis for design against fatigue failure of htr components

Hermann Diehl, Izabella Blume-firla, Wolfgang Mergler

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 519 KB

english, 1990

10

Estimation of crack growth in the creep range during plastic cyclic loading

M. Kullik, K. Maile

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 653 KB

english, 1990

11

Influence of damage mechanisms on the creep crack growth behaviour of x 20 CrMoV 12 1 at 550°C

G. Gnirβ, W. Hartnagel, B. Trück

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.20 MB

english, 1990

12

Analysis of the deformation and damage development of a dissimilar weld operating in the creep regime

Klaus Schneider, Erich Tolksdorf, Günter Gnirβ

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.63 MB

english, 1990

13

Evaluation of fatigue of reactor components by on-line monitoring of transients

M. Miksch, G. Schücktanz

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 610 KB

english, 1990

14

The method of “local approach of fracture” and its application to a thermal shock experiment

M. Bethmont, G. Rousselier, K. Kussmaul, A. Sauter, A. Jovanovic

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.05 MB

english, 1990

15

Analysis of crack behaviour in the jrc ispra pressurized thermal shock experiment

A. Jovanovic, A.C. Lucia

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.29 MB

english, 1990

16

3D-FE-calculations of a pressure vessel under thermal shock loading

R. Stegmeyer, A. Sauter, A. Höfler, J. Sievers, H. Kordisch

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 330 KB

english, 1990

17

Behaviour of surface flaws under thermal-mechanical loading

A. Sauter, T. Nguyen-Huy, U. Weber, H. Huber

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.78 MB

english, 1990

18

Elastic-plastic fracture mechanics analysis of a pressure vessel with an axial outer surface flaw

W. Brocks, G. Künecke

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 559 KB

english, 1990

19

Component testing at the HDR-facility for validating the calculation procedures and the transferability of test results from specimen to component

G. Katzenmeier, K. Kussmaul, E. Roos, H. Diem

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 809 KB

english, 1990

20

Structural integrity of lmfbrs including leak before break

K. Vinzens, H. Laue, B. Hosemann

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 433 KB

english, 1990

21

Initiation and instability behaviour of cracked lmfbr piping: comparison of different theoretical approaches and experiments

S. Bhandari, D. Nesa, C. Faidy, L. Grüter

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 500 KB

english, 1990

22

Fracture mechanics study of a pipe bend with a longitudinal crack under static loading

Dietmar Uhlmann, Harald Diem, Stefan Brosi

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 813 KB

english, 1990

23

Resonant excitation of a pipe section

K. Kerkhof, W. Stoppler, D. Sturm, R. Zirn

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 791 KB

english, 1990

24

Environmentally assisted crack growth in low alloy steels — results and their relevance to lwr components

E. Tenckhoff, M. Erve, E. Lenz, G. Vazoukis

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 488 KB

english, 1990

25

Fatigue crack growth in reactor pressure vessel materials and light water reactor environments

W.A. Van Der Sluys, R.H. Emanuelson

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 593 KB

english, 1990

26

Stress corrosion and thermal fatigue — Experiences and countermeasures in austenitic SS pipings of finnish bwr-plants

J. Hakala, H HÄnninen, P. Aaltonen

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.12 MB

english, 1990

27

Stress corrosion in low alloy steels

P.M. Scott, D.R. Tice

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.26 MB

english, 1990

28

Environmentally assisted crack growth in a low alloy boiler steel in high temperature water containing oxygen

K. Kussmaul, B. Iskluth

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.77 MB

english, 1990

29

Calculation code for erosion corrosion induced wall thinning in piping systems

W. Kastner, M. Erve, N. Henzel, B. Stellwag

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 767 KB

english, 1990

30

Influence of contact conditions on vibration induced wear of metals

P.J. Hofmann, T. Schettler, N. Wieling, D.A. Steininger

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 467 KB

english, 1990

31

Ceramic coatings for protection against frictional wear and diffusion welding in HTR helium

W. Theymann, R. Engel, H. Demus

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.36 MB

english, 1990

32

Monitoring the filling level of the rpv using stationary emus-probes

G HÜbschen, E LÖhr, A. Walleser

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.89 MB

english, 1990

33

The measurement of transient deformation by double pulsed interferometry, a method for nondestructive testing

M. Hajduk, D. Mewes

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.78 MB

english, 1990

34

PISC full scale reactor pressure vessel validation of non-destructive examination

S. Crutzen, H. Herkenrath, K. Kussmaul, U. Mletzko

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 3.51 MB

english, 1990

35

Author index to volume 119

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 216 KB

english, 1990

36

Subject index to volume 119

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 173 KB

english, 1990

To build up a library is to create a life. It’s never just a random collection of books.

— Carlos María Domínguez

Official channel

Z-Library Desktop Launcher

Tor version

Z-Library

Z-Library Since 2009 support@1delivery.pm

EnglishРусскийEspañolItalianoελληνικάاللغة العربيةBahasa IndonesiaBahasa Malaysiaहिन्दीDeutschFrançaisPortuguêsУкраїнськаPolski中文繁體中文日本語Tiếng ViệtAzərbaycan DiliՀայոց լեզուภาษาไทยTürk Diliქართველიবাংলাپښتوతెలుగుاردو한국어SrpskiБългарски