Cladding circumferential hot spot factors for fuel and blanket rods-Reference-Cited by-同舟云学术

Cladding circumferential hot spot factors for fuel and blanket rods

Published:1975-01 Issue:1 Volume:35 Page:21-28
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chuang M.C.,Kothmann R.E.,Pechersky M.J.,Markley R.A.

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

Reference5 articles.

1. Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire wrap spacer system;Novendstern;Nucl. Eng. Des.,1972

2. Hydraulic resistance and heat transfer in a turbulent liquid stream in a lattice of rods;Buleev;High Temperature, USSR,1964

3. Turbulent-flow heat transfer for in-line flow through unbaffled rod bundles: molecular conduction only;Dwyer;Nucl. Sci. Eng.,1971

4. Analysis of liquid metal heat transfer in assemblies of closely spaced fuel rods;Nijsing;Nucl. Eng. Des.,1969

5. 11:1 scale rod bundle flow tests, parts 1 through 7;Pechersky;WARD-OX-3045-6, USAEC,1974

Cited by 5 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. Development and Application of an Integrated Fuel Performance and Subchannel Model for Analysis of Sodium Fast Reactors;Nuclear Technology;2013-10

2. Development of finite element analysis code SPOTBOW for prediction of local velocity and temperature fields around distorted fuel pin in LMFBR assemblies;J NUCL SCI TECHNOL;1996

3. Development of Finite Element Analysis Code SPOTBOW for Prediction of Local Velocity and Temperature Fields around Distorted Fuel Pin in LMFBR Assemblies;Journal of Nuclear Science and Technology;1996-05

4. Heat transfer, momentum losses and flow mixing in a 61-tube bundle with wire-wrap;Nuclear Engineering and Design;1979-12

5. Three-Dimensional Thermal-Hydraulic Analysis of Wire-Wrapped Rods in Liquid-Metal Fast Breeder Reactor Core Assemblies;Nuclear Science and Engineering;1977-09