Application of advanced validation concepts to oxide fuel performance codes: LIFE-4 fast-reactor and FRAPCON thermal-reactor fuel performance codes-Reference-Cited by-同舟云学术

Application of advanced validation concepts to oxide fuel performance codes: LIFE-4 fast-reactor and FRAPCON thermal-reactor fuel performance codes

Published:2013-10 Issue: Volume:263 Page:102-128
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Unal C.,Williams B.J.,Yacout A.,Higdon D.M.

Funder

US Department of Energy, Nuclear Energy Division, Advanced Modeling and Simulation Office (NE-71)

Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program, Verification, Validation and Uncertainty Quantification (VU)

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

1. Advancement in the behavior modeling of fuel elements and related structures;Billone;Nucl. Eng. Des.,1992

2. Diffusion theory of fission gas migration in irradiated nuclear fuel UO2;Forsberg;J. Nucl. Mater.,1985

3. Geelhood, K., et al., 2011a. FRAPCON-3.4: A Computer Code for the Calculation of Steady-State Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup Technical Report. Office of Nuclear Regulatory Research, NUREG/CR-7022, vol. 1.

4. Geelhood, K., et al., 2011b. FRAPCON-3.4: Integral Assessment Technical Report. Office of Nuclear Regulatory Research, NUREG/CR-7022, vol. 2.

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