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