1 |
U.S. Nuclear Regulatory Commission, Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory Requirements (Rep. No. SECY-90-016), U.S. Nuclear Regulatory Commission, Washington, D.C., 1990.
|
2 |
U.S. Nuclear Regulatory Commission, Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants (Rep. No. NUREG-1150), U.S. Nuclear Regulatory Commission, Washington, D.C., 1990.
|
3 |
M.F. Hessheimer, R.A. Dameron, Containment Integrity Research at Sandia National Laboratories: An Overview (Rep. No. NUREG/CR-6906, SAND2006-2274P), Sandia National Laboratories, Albuquerque, NM, 2006.
|
4 |
B.W. Spencer, J.P. Petti, D.M. Kunsman, Risk-Informed Assessment of Degraded Containment Vessels (Rep. No. NUREG/CR-6920, SAND2006-3772P), Sandia National Laboratories, Albuquerque, NM, 2006.
|
5 |
J.P. Petti, D.A. Kalinich, J. Jun, K.C. Wagner, Effects of Degradation on the Severe Accident Consequences for a PWR Plant with a Reinforced Concrete Containment Vessel (Rep. No. NUREG/CR-7149, SAND2009-6323P), Sandia National Laboratories, Albuquerque, NM, 2013.
|
6 |
N. Buratti, C. Mazzotti, M. Savoia, Post-cracking behaviour of steel and macro-synthetic fibre-reinforced concretes, Constr. Build. Mater. 25 (2011) 2713-2722.
DOI
|
7 |
S.P. Shah, B.V. Rangan, Fiber reinforced concrete properties, ACI J. 68 (1971) 126-135.
|
8 |
H.H. Abrishami, D. Mitchell, Influence of steel fibers on tension stiffening, ACI Struct. J. 94 (1997) 769-775.
|
9 |
P.H. Bischoff, Tension stiffening and cracking of steel fiberreinforced concrete, J. Mater. Civ. Eng. 15 (2003) 174-182.
DOI
|
10 |
J.R. Deluce, F.J. Vecchio, Cracking behavior of steel fiber-reinforced concrete members containing conventional reinforcement, ACI Struct. J. 110 (2013) 481-490.
|
11 |
I. Lofgren, Fibre-Reinforced Concrete for Industrial Construction: A Fracture Mechanics Approach to Material Testing and Structural Analysis, PhD Thesis, Department of Civil and Environmental Engineering, Chalmers University of Technology, Goteborg, Sweden, 2005.
|
12 |
M.F. Hessheimer, E.W. Klamerus, L.D. Lambert, G.S. Rightley, R.A. Dameron, Overpressurization Test of a 1:4-Scale Prestressed Concrete Containment Vessel Model (Rep. No. NUREG/CR-6810, SAND2003-0840P), Sandia National Laboratories, Albuquerque, NM, 2003.
|
13 |
ABAQUS FEA, ABAQUS/Standard 6.8-User's Manual, Hibbitt, Karlsson & Sorensen, Inc., Providence, RI, 2008.
|
14 |
U.S. Nuclear Regulatory Commission, Containment Structural Integrity Evaluation for Internal Pressure Loadings above Design-Basis Pressure (Regulatory Guide 1.216), U.S. Nuclear Regulatory Commission, Washington, D.C., 2010.
|