Science and Technology of Nuclear Installations

Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept

Monitoring of ²²⁰Rn Concentrations in Buildings of Kufa Technical Institute, Iraq

Method of Measuring the Efficiency of the Conversion of Nuclear Energy into Optical Energy

Prediction of Flow Regimes and Thermal Hydraulic Parameters in Two-Phase Natural Circulation by RELAP5 and TRACE Codes

Study of the Reactor Control System of MSHIM in AP1000

NaI(Tl) Detector Efficiency Computation Using Radioactive Parallelepiped Sources Based on Efficiency Transfer Principle

Thermal-Hydraulic Assessment of W7-X Plasma Vessel Venting System in Case of 40 mm In-Vessel LOCA

An Innovative Passive Residual Heat Removal System of an Open-Pool Type Research Reactor with Pump Flywheel and Gravity Core Cooling Tank

Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP

Temperature Response of the HTR-10 during the Power Ascension Test

Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysis

Advanced Integral Type Reactors: Passive Safety Design and Experiment

Input Calibration and Validation of RELAP5 Against CIRCUS-IV Single Channel Tests on Natural Circulation Two-Phase Flow Instability

Study on the Effects of Liquid Thermal Media on the Irradiation Capsule of High-Temperature Materials

Integrated Deterministic and Probabilistic Safety Analysis for Safety Assessment of Nuclear Power Plants

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2015

Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept

Monitoring of ²²⁰Rn Concentrations in Buildings of Kufa Technical Institute, Iraq

Method of Measuring the Efficiency of the Conversion of Nuclear Energy into Optical Energy

Prediction of Flow Regimes and Thermal Hydraulic Parameters in Two-Phase Natural Circulation by RELAP5 and TRACE Codes

Study of the Reactor Control System of MSHIM in AP1000

NaI(Tl) Detector Efficiency Computation Using Radioactive Parallelepiped Sources Based on Efficiency Transfer Principle

Thermal-Hydraulic Assessment of W7-X Plasma Vessel Venting System in Case of 40 mm In-Vessel LOCA

An Innovative Passive Residual Heat Removal System of an Open-Pool Type Research Reactor with Pump Flywheel and Gravity Core Cooling Tank

Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP

Temperature Response of the HTR-10 during the Power Ascension Test

Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysis

Advanced Integral Type Reactors: Passive Safety Design and Experiment

Input Calibration and Validation of RELAP5 Against CIRCUS-IV Single Channel Tests on Natural Circulation Two-Phase Flow Instability

Study on the Effects of Liquid Thermal Media on the Irradiation Capsule of High-Temperature Materials

Integrated Deterministic and Probabilistic Safety Analysis for Safety Assessment of Nuclear Power Plants

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2015

Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept

Monitoring of 220Rn Concentrations in Buildings of Kufa Technical Institute, Iraq

Method of Measuring the Efficiency of the Conversion of Nuclear Energy into Optical Energy

Prediction of Flow Regimes and Thermal Hydraulic Parameters in Two-Phase Natural Circulation by RELAP5 and TRACE Codes

Study of the Reactor Control System of MSHIM in AP1000

NaI(Tl) Detector Efficiency Computation Using Radioactive Parallelepiped Sources Based on Efficiency Transfer Principle

Thermal-Hydraulic Assessment of W7-X Plasma Vessel Venting System in Case of 40 mm In-Vessel LOCA

An Innovative Passive Residual Heat Removal System of an Open-Pool Type Research Reactor with Pump Flywheel and Gravity Core Cooling Tank

Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP

Temperature Response of the HTR-10 during the Power Ascension Test

Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysis

Advanced Integral Type Reactors: Passive Safety Design and Experiment

Input Calibration and Validation of RELAP5 Against CIRCUS-IV Single Channel Tests on Natural Circulation Two-Phase Flow Instability

Study on the Effects of Liquid Thermal Media on the Irradiation Capsule of High-Temperature Materials

Integrated Deterministic and Probabilistic Safety Analysis for Safety Assessment of Nuclear Power Plants

Monitoring of ²²⁰Rn Concentrations in Buildings of Kufa Technical Institute, Iraq