Published 2006 | Version v1
Book

Whole Core Sub-Channel Analysis Verification with the EBR-II SHRT-17 Test

  • 1. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (United States)
  • 2. Korea Atomic Energy Research Institute, Yusong, P.O. Box 105, Daejon, 305-600 (Korea, Republic of)

Description

As part of an International Nuclear Energy Research Initiative, Argonne National Laboratory and the Korea Atomic Energy Research Institute have cooperated in developing a detailed whole core coolant sub-channel model. This model has been implemented in LMR systems codes and coupled with the primary loop treatments in these codes. Analysis of the SHRT-17 test performed in the EBR-II reactor has been used for verification of the model. Detailed steady-state and transient coolant temperature profiles and subassembly flow rates are available for an instrumented subassembly that was in the core for this test. Calculated coolant temperatures and flow rates agree well with the measured values. (authors)

Part of:
Validation of the TRACE Code Against Post-Dryout Experiments in Tubes and Annuli

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448-698-5
Imprint Title
Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06
Imprint Pagination
2734 p.
Journal Page Range
p. 1601-1607

Conference

Title
2006 International congress on advances in nuclear power plants - ICAPP'06
Dates
4-8 Jun 2006
Place
Reno - Nevada (United States)

INIS

Optional Information

Notes
10 refs.