Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding-Reference-Cited by-同舟云学术

Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding

Published:2016-02 Issue:1 Volume:48 Page:16-25
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Cheng Bo,Kim Young-Jin,Chou Peter

Funder

EPRI Technology Innovation Program

Fuel Reliability Program

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference9 articles.

1. Fuel behavior in severe accidents and Mo-alloy based cladding to improve accident tolerance;Cheng,2012

2. Application of MELCOR to ATF Concepts for Severe Accident Analysis, Presented at EPRI/INL/DOE Workshop on Accident Tolerant Fuel;Bragg Sitten,2014

3. B. Cheng, P. Chou, Y. J. Kim, Feasibility evaluations of Mo-alloy cladding to enhance accident tolerance, Paper #0204, TopFuel, Zurich (Switzerland), September 14, 2015.

4. IAEA Symposium on Accident Tolerant Fuel Concepts for Light Water Reactors,2014

5. Irradiation hardening in unalloyed and ODS molybdenum during low dose neutron irradiation at 300° C and 600° C;Cockeram;J. Nucl. Mater.,2008

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