Core Thermohydraulic Design With 20% LEU Fuel for Upgraded Research Reactor JRR-3

Journal of Nuclear Science and Technology - United Kingdom
doi 10.1080/18811248.1985.9735696
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Informa UK Limited

Related search

The Thermohydraulic Analysis of the Bandung Research Reactor Core With Plate Type Fuel Elements Using the CFD Code

JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA
2018English

Safety Analysis for the WWR-K Research Reactor Converted to LEU Fuel

Eurasian Journal of Physics and Functional Materials
2019English

Preliminary LEU Fuel Cycle Analyses for the Belgian BR2 Reactor

1986English

Foreign Research Reactor Irradiated Nuclear Fuel Inventories Containing HEU and LEU of United States Origin

1994English

High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor

2010English

10 CFR 830 Major Modification Determination for Advanced Test Reactor LEU Fuel Conversion

2012English

Use of Neutron Filters for Fast Reactor Fuel Irradiations in a Thermal Reactor Core.

1966English

Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design

2010English

Study of the Self-Controllability for the Fast Reactor Core With High-Thermal-Conductivity Fuel

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
2010English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2024 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy