Published April 2016 | Version v1
Miscellaneous

Validation of PUCHOK-LM subchannel thermal-hydraulic code as applied to MBIR reactor

  • 1. Valery Shishov Nuclear Energy, NIKIET, ROSATOM (Russian Federation)

Description

The systematized results of PUCHOK-LM code validation based on experimental data are presented. The code, developed at JSC NIKIET, is designed for steady-state thermal-hydraulic analysis of fast-neutron liquid-metal-cooled reactor fuel assemblies by subchannel method. This work considers the use of PUCHOK-LM code as applied to the sodium-cooled reactor. The general structure of the code, mathematical models and closing dependencies are described in brief . The calculation results of temperature fields agree with experimental dates for the region of maximum coolant heat-ups in a range of 12%

Part of:
28. conference of the Nuclear Societies in Israel. Program and papers

Additional details

Publishing Information

Publisher
NSI
Imprint Place
Tel Aviv (Israel)
Imprint Title
28. conference of the Nuclear Societies in Israel. Program and papers
Imprint Pagination
355 p.
Series
Proceedings Series
Journal Page Range
1 p.
Report number
INIS-IL--23

Conference

Title
28. conference of the Nuclear Societies in Israel
Dates
12-14 Apr 2016
Place
Tel Aviv (Israel)

Optional Information