TRACE code core reflood thermal-hydraulics phenomena benchmarking against the NRC–PSU Rod Bundle Heat Transfer (RBHT) test facility-Reference-Cited by-同舟云学术

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TRACE code core reflood thermal-hydraulics phenomena benchmarking against the NRC–PSU Rod Bundle Heat Transfer (RBHT) test facility

Published:2024-12 Issue: Volume:429 Page:113539
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Garrett Grant R.^ORCID,Miller Douglas J.,Almudhhi Turki,Cheung Fan-Bill,Lowery Brian R.,Hanson Molly K.,Bajorek Stephen M.,Tien Kirk,Hoxie Chris L.

Funder

U.S. Nuclear Regulatory Commission

Publisher

Elsevier BV

Reference37 articles.

1. Implementation of a three-field framework in TRACE to improve the prediction of reactor core reflood conditions Part II;Al-Yahia,2023

2. Experimental investigation of minimum film boiling temperature during reflood transients;Almudhhi,2023

3. Trace Calculation Notebook;Bajorek,2007

4. TRACE V5.0 PATCH 5 THEORY MANUAL Field Equations, Solution Methods, and Physical Models;Bajorek,2017

5. TRACE V5.0 Patch 5 Theory Manual;Bajorek,2017

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