Published March 2015 | Version v1
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Development of thermal-hydraulic design code for transmutation system with lead-bismuth cooled accelerator driven reactor

  • 1. Japan Atomic Energy Agency, Sector of Nuclear Science Research, Nuclear Science and Engineering Center, Tokai, Ibaraki (Japan)

Description

A thermal-hydraulic analysis code for transmutation system with lead-bismuth cooled accelerator-driven system (ADS) has been developed using the Japanese-version of Transient Analysis Code (J-TRAC) as the framework in order to apply the design studies of ADS. To identify the required capabilities of the thermal-hydraulic analysis code for ADS, previous thermal-hydraulic analyses of pressurized water reactor, boiling water reactor, sodium-cooled fast reactor and ADS have been surveyed. To make up for insufficient capabilities of the J-TRAC code as a thermal-hydraulic analysis code of ADS, physical properties of lead-bismuth eutectic (LBE), argon gas and nitride nuclear fuel were implemented to the J-TRAC code. It was confirmed that the implemented capabilities worked as expected through verification calculations on (1) the pressure loss in a single-phase LBE flow, (2) the heat transfer in a fuel assembly including nitride nuclear fuel, and (3) the heat transfer between LBE and water in a steam generator. (author)

Availability note (English)

Available from JAEA; DOI: https://doi.org/10.11484/jaea-data-code-2014-031

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Publishing Information

Imprint Pagination
86 p.
Report number
JAEA-Data/Code--2014-031

Optional Information

Notes
19 refs., 43 figs., 15 tabs.