Benchmarking of thermal hydraulic loop models for Lead-Alloy Cooled Advanced Nuclear Energy System (LACANES), phase-I: Isothermal steady state forced convection

Author:

Cho Jae Hyun,Batta A.,Casamassima V.,Cheng X.,Choi Yong Joon,Hwang Il Soon,Lim Jun,Meloni P.,Nitti F.S.,Dedul V.,Kuznetsov V.,Komlev O.,Jaeger W.,Sedov A.,Kim Ji Hak,Puspitarini D.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference25 articles.

1. Handbook on Lead–Bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal–Hydraulics and Technologies, 2007 edition, NEA No. 6195.

2. OECD/NEA, Benchmarking of Thermal–Hydraulic Loop Models for Lead-alloy Cooled Advanced Nuclear Energy Systems (LACANES) – Task Guideline for Phase 1: Characterization of HELIOS, 2007.

3. Use of lead-bismuth coolant in nuclear reactors and accelerator-driven systems

4. Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects, severe safety and economical issues

5. Proposal for pressure drop prediction for a fuel bundle with grid spacers using Rehme pressure drop correlations

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