Results: 1-25 | 26-50 | 51-75 | 76-100 | >>

Table of contents of journal: *Nuclear engineering and design

Results: 51-75/2165

Authors: Saxena, AK Raj, VV Rao, VG
Citation: Ak. Saxena et al., Experimental studies on rewetting of hot vertical annular channel, NUCL ENG DE, 208(3), 2001, pp. 283-303

Authors: Sawa, K Suzuki, S Shiozawa, S
Citation: K. Sawa et al., Safety criteria and quality control of HTTR fuel, NUCL ENG DE, 208(3), 2001, pp. 305-313

Authors: Jackson, DA Doctor, SR Schuster, G Simonen, F
Citation: Da. Jackson et al., Developing a generalized flaw distribution for reactor pressure vessels, NUCL ENG DE, 208(2), 2001, pp. 123-131

Authors: Vander Molen, HJ
Citation: Hj. Vander Molen, Enhancing regulatory effectiveness by improving the process for identifying and resolving generic issues, NUCL ENG DE, 208(2), 2001, pp. 133-142

Authors: Simonen, FA Khaleel, MA Phan, HK Harris, DO Dedhia, DD Kalinousky, DN Shaukat, SK
Citation: Fa. Simonen et al., Evaluation of environmental effects on fatigue life of piping, NUCL ENG DE, 208(2), 2001, pp. 143-165

Authors: Majumdar, S
Citation: S. Majumdar, Structural analysis of electrosleeved tubes under severe accident transients, NUCL ENG DE, 208(2), 2001, pp. 167-179

Authors: Diamond, DJ Aronson, A Jo, J Avvakumov, A Malofeev, V Sidorov, V Ferraresi, P Gouin, C Aniel, S Royer, ME
Citation: Dj. Diamond et al., Intercomparison of results for a PWR rod ejection accident, NUCL ENG DE, 208(2), 2001, pp. 181-189

Authors: Ducros, G Malgouyres, PP Kissane, M Bouland, D Durin, M
Citation: G. Ducros et al., Fission product release under severe accidental conditions: general presentation of the program and synthesis of VERCORS 1-6 results, NUCL ENG DE, 208(2), 2001, pp. 191-203

Authors: Cousinou, P Lavarenne, C Biron, D Doucet, M Grouiller, JP Thiollay, N Guillou, E
Citation: P. Cousinou et al., Taking burnup credit into account in criticality studies: the situation asit is now and the prospect for the future, NUCL ENG DE, 208(2), 2001, pp. 205-214

Authors: Kussmaul, K
Citation: K. Kussmaul, Topical issue - 27th Water Reactor Safety Information Meeting (WRSM) - Bethesda, MD, USA - 25-27 October 1999 - Preface, NUCL ENG DE, 208(2), 2001, pp. V-V

Authors: Shibata, K Kato, D Li, YS
Citation: K. Shibata et al., Development of a PFM code for evaluating reliability of pressure components subject to transient loading, NUCL ENG DE, 208(1), 2001, pp. 1-13

Authors: Raza, SS Avila, R Cervantes, J
Citation: Ss. Raza et al., A 3-D Lagrangian stochastic model for the meso-scale atmospheric dispersion applications, NUCL ENG DE, 208(1), 2001, pp. 15-28

Authors: El-Genk, MS Tournier, JM
Citation: Ms. El-genk et Jm. Tournier, Performance analysis of coated plutonia particle fuel compact for radioisotope heater units, NUCL ENG DE, 208(1), 2001, pp. 29-50

Authors: Cotton, MA Ismael, JO Kirwin, PJ
Citation: Ma. Cotton et al., Computations of post-trip reactor core thermal hydraulics using a strain parameter turbulence model, NUCL ENG DE, 208(1), 2001, pp. 51-66

Authors: Kiger, KT Gavelli, F
Citation: Kt. Kiger et F. Gavelli, Boron mixing in complex geometries: flow structure details, NUCL ENG DE, 208(1), 2001, pp. 67-85

Authors: Cosandey, JO von Rohr, PR
Citation: Jo. Cosandey et Pr. Von Rohr, Entrainment of soluble and non soluble tracers from a boiling water surface, NUCL ENG DE, 208(1), 2001, pp. 87-97

Authors: Choi, YS Lee, UJ Park, GC
Citation: Ys. Choi et al., Study on local hydrogen behaviors in a subcompartment of the NPP containment, NUCL ENG DE, 208(1), 2001, pp. 99-116

Authors: Minematsu, A
Citation: A. Minematsu, Current topics of the structural design for LWR plants in Japan, NUCL ENG DE, 207(3), 2001, pp. 257-267

Authors: Yagawa, G Kanto, Y Yoshimura, S Machida, H Shibata, K
Citation: G. Yagawa et al., Probabilistic fracture mechanics analysis of nuclear structural components: a review of recent Japanese activities, NUCL ENG DE, 207(3), 2001, pp. 269-286

Authors: Isobe, Y Sagisaka, M Yoshimura, S Yagawa, G
Citation: Y. Isobe et al., Risk-benefit analyses of SG tube maintenance based on probabilistic fracture mechanics, NUCL ENG DE, 207(3), 2001, pp. 287-298

Authors: Kupperman, DA Bakhtiari, S Muscara, J
Citation: Da. Kupperman et al., Steam generator mock-up for assessment of inservice inspection technology, NUCL ENG DE, 207(3), 2001, pp. 299-305

Authors: Michel, F Reck, H Schulz, H
Citation: F. Michel et al., Experience with piping in German NPPs with respect to ageing-related aspects, NUCL ENG DE, 207(3), 2001, pp. 307-316

Authors: Nishida, Y
Citation: Y. Nishida, Non-destructive diagnosis technique for aging of cables used at nuclear power plants, NUCL ENG DE, 207(3), 2001, pp. 317-325

Authors: Bhandari, S Dubois, D Guichard, D
Citation: S. Bhandari et al., Behaviour of a PWR vessel dissimilar metal weld during a steam line break transient, NUCL ENG DE, 207(3), 2001, pp. 327-339

Authors: Yoo, YS Ando, K
Citation: Ys. Yoo et K. Ando, Plastic collapse and LBB behavior of statically indeterminate piping system subjected to a static load, NUCL ENG DE, 207(3), 2001, pp. 341-350
Risultati: 1-25 | 26-50 | 51-75 | 76-100 | >>