1981 - SMiRT 6 - Paris, France
Permanent URI for this collectionhttps://www.lib.ncsu.edu/resolver/1840.20/42094
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Browsing 1981 - SMiRT 6 - Paris, France by Division "C - Analysis of Reactor Fuel and Cladding Materials"
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- A Failure Criterion for Zircaloy Fuel Sheath Under LOCA Conditions(IASMiRT, 1981-08-17) T. Cheung; H.E. Rosinger
- A Phenomenological Model for Iodine Stress Corrosion Cracking of Zircaloy(IASMiRT, 1981-08-17) A.K. Miller; A. Tasooji
- A Simplified Method to Account for Irradiation Effects in the Structure Analysis of HTR Core Components(IASMiRT, 1981-08-17) H. Tobbe; J.G. Willaschek
- A Universal Model for Coated Particle Failure(IASMiRT, 1981-08-17) K. Bongartz; H. Nabielek
- Compliance Characteristics of Cracked U02 Pellets(IASMiRT, 1981-08-17) R.E. Williford; C.L. Mohr; D.D. Lanning
- Cracking and Relocation of U02 Fuel During Nuclear Operation(IASMiRT, 1981-08-17) A.D. Appelhans; S.J. Dagbjartsson
- Do Radial Gradients of Swelling and Mechanical Properties Induce an Additional Diameter Increase in LMFBR Fuel Pins? (Est-ce que des gradients radiaux de gonflement et de proprietes mecaniques peuvent creer des deformations supplementaires de l’lment combustible rapide?)(IASMiRT, 1981-08-17) P. Lemoine; J.L. Boutard; Y. Guerin
- Failure of Metallic-Fuel Cladding During Strain Transients(IASMiRT, 1981-08-17) J.C. Rawers; J.A. Buzzell; G.M. Schwartzenberger; G.D. Hudman
- Fracture Mechanics Investigations on Crack Propagation in Graphite Reactor Components under Strain-Controlled Loads(IASMiRT, 1981-08-17) A. Schmidt; G. Kraus
- Influence of Final Annealing on Mechanical Properties of Zircaloy Before and After Irradiation(IASMiRT, 1981-08-17) F. Garzarolli; R. Manzel; H. Schonfeld; E. Steinberg
- Investigation of Stress Corrosion Cracking in Zircaloy Tubing with Respect to the PCI Phenomenon(IASMiRT, 1981-08-17) M. Peehs; W. Jung; H. Stehle; E. Steinberg
- Modeling Solid-Fuel Dispersal During Slow Loss-of-Flow-Type Transients(IASMiRT, 1981-08-17) R.J. DiMelfi; G.R. Fenske
- Modeling the Transient Failure Behavior of Irradiated Fast Reactor Cladding Tubes Including Fuel-Adjacency Effects(IASMiRT, 1981-08-17) R.J. DiMelfi; J.M. Kramer
- On Thermomechanical Behaviour of Irradiated Fuel Sheath(IASMiRT, 1981-08-17) T.R. Hsu; Y.J. Kim
- Prediction of Coated Particle Behaviour under Irradiation with the Code IAMESI and Comparison with Experiments(IASMiRT, 1981-08-17) H.-L. Gehr; A.-W. Mehner
- Response of Fission Gas to Nearly Isothermal Heating of UO2 Fuel From Decay Heat(IASMiRT, 1981-08-17) W. Steele; A.R. Wazzan; D. Okrent
- Temperative Estimates from the Zircaloy Oxidation Kinetics in the α plus β Phase Region(IASMiRT, 1981-08-17) C.S. Olsen
- Tensile, Creep and Relaxation Characteristics of Zircaloy Cladding at 385 °C(IASMiRT, 1981-08-17) K.L. Murty; S.G. McDonald
- The Begin-of.-Life-Behaviour of Fast Breeder Reactor Fuel Pins: Irradiation Tests and Verification of Restructuring Models(IASMiRT, 1981-08-17) H. Steiner; B. Steinmetz; J. Van Vliet; P. Zeisser
