Thermal-Hydraulic Analysis of a Research Reactor on Personal Computer With TARR Code

Vietnam Journal of Mechanics
doi 10.15625/0866-7136/10233
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Publishing House for Science and Technology, Vietnam Academy of Science and Technology

Related search

A Three-Dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal Hydraulic Computer Code

1990English

SUPERENERGY-2: A Multiassembly, Steady-State Computer Code for LMFBR Core Thermal-Hydraulic Analysis

1980English

Thermal-Hydraulic Hot-Spot Analysis of IRT-5000 Nuclear Research Reactor: Comparative Safety Evaluation

FME Transactions
Mechanics of MaterialsMechanical Engineering
2019English

A Validation of ATR LOCA Thermal-Hydraulic Code With a Statistical Approach

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
2000English

Pebble Bed Reactor Program. Coolball: A Machine Code for Thermal Analysis of Pebble Bed Reactor Cores

1960English

High Heat Program, Thermal Hydraulic Computer Models

1998English

Thermal Hydraulic Analysis of the Regimes With Unmanageable Control Rods Movement and Ejection for the Reactor Strength Estimation

Odes’kyi Politechnichnyi Universytet. Pratsi
2017English

Thermal and Hydraulic Design of the Consolidated Edison Thorium Reactor

1960English

Advanced Neutron Source Reactor Thermal-Hydraulic Test Loop Facility Description

1994English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2025 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy