Prediction of maximum temperature or melting fraction in a LMFBR fuel element-Reference-Cited by-同舟云学术

Prediction of maximum temperature or melting fraction in a LMFBR fuel element

Published:1971-12 Issue:3 Volume:17 Page:361-370
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Thompson D.H.,Marr W.W.

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

Reference12 articles.

1. A Three-region Analytical Model for the Description of the Thermal Behavior of Low-density Oxide Fuel Rods in a Fast-reactor Environment;Sayles;Trans. Amer. Nucl. Soc.,1967

2. 1000-MWe Liquid Metal Fast Breeder Reactor Follow-on Study Conceptual Design Report, Volume II, Engineering Studies;Atomics International;USAEC report No. AI-AEC-12792,1969

3. Thermal Conductivity of Uranium-Plutonium Oxide Fuels;Baily,1968

4. Heat Transfer Coefficients between Fuel and Cladding in Oxide Fuel Rods;Craig;USAEC report No. GEAP-5748,1969

5. Theoretical and Computer Analysis on the Behavior of Fast Reactor Fuel Pins and Related Parts of the Core Under Operational Conditions;Karsten;Report KFK 878,1968

Cited by 7 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Transient temperature distribution in the reactor vessel wall;Nuclear Engineering and Design;1979-05

2. Boundary-Value Thermal-Hydraulic Analysis of a Reactor Fuel Rod Bundle;Nuclear Science and Engineering;1976-02-01

3. A computation method for the steady state thermohydraulic analysis of fuel rod bundles with single phase cooling;Nuclear Engineering and Design;1974-09

4. Heat transfer in LMFBR fuel elements Part II: Effects of fuel pellet cracks, granular fuel structure and azimuthally non-uniform heat transfer from cladding to bulk coolant;Nuclear Engineering and Design;1974-02

5. Heat transfer in LMFBR fuel elements Part I: Effects of fuel pellet displacement;Nuclear Engineering and Design;1974-02