Published April 15, 2016 | Version v1
Journal article

10 MW research reactor simulation using fuel plate type

  • 1. Reactors Department, Nuclear Researches Center, Inshas (Egypt)
  • 2. Mechanical Power Engineering Department, Faculty of Engineering, Al Azhar University, Cairo (Egypt)

Description

A computer code was established named ET-RR-1-10 to investigate the thermal hydraulic behavior of the ETRR1 (first Egyptian research reactor) research reactor when its power upgraded to 10 MW using the new fuel plate elements type. The work done include both normal and flow reduction conditions. The code modeled primary loop, secondary lop, and reactor kinetics. All code models used finite difference technique. The code results were tested against the available corresponding experimental data taken from a similar research reactor MITR (Massachusetts Institute of Technology research reactor) for the sake of code validation. The results showed good agreement, and the code can be used for thermal hydraulic calculations.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2016.01.006

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2016.01.006;
PII
S0029-5493(16)00016-9;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
300
Journal Page Range
p. 34-40
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
48005634
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
COMPUTERIZED SIMULATION; E CODES; FUEL PLATES; REACTOR KINETICS; RESEARCH REACTORS; THERMAL HYDRAULICS; VALIDATION
Descriptors DEC
COMPUTER CODES; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; KINETICS; MECHANICS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; TESTING

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.