Variable moderation high performance light water reactor (VMHWR)
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference19 articles.
1. Studies on supercritical water reactor fuel assemblies using the sub-channel code COBRA-EN;Ammirabile;Nucl. Eng. Des.,2010
2. American Standard Atomic Energy Div., March 1958, A Power Reactor Moderator Level Controlled. Bull 107.
3. Validation of Coupled Neutron Physics and Thermal Hydraulic Analysis for HPLWR. ICAPP;Broeders,2003
4. Design analysis of core assemblies for supercritical pressure conditions;Cheng;Nucl. Eng. Des.,2003
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1. Thermal-hydraulic analysis of a novel design super critical water reactor with Al2O3 nanofluid as a coolant;The Journal of Supercritical Fluids;2018-10
2. Neutronic Analysis of Heavy Water Application in HPLWR Emergency Core Cooling System;Arab Journal of Nuclear Sciences and Applications;2018-04-01
3. NEUTRONIC INVESTIGATION OF SEMI-HEAVY WATER APPLICATION IN HPLWR NEW FLOW PATTERN;CNL Nuclear Review;2016-09-28
4. Neutronic analysis of a superheat BWR using high performance fuel rod technique;Progress in Nuclear Energy;2016-09
5. Axial enrichment profile in advance nuclear energy power plant at supercritical-pressures;Kerntechnik;2015-12-12
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