Acceptance Test of Graphite Components in Nuclear Reactor

Computing Atomic Density Changes of Material Composition in Operation of the Nuclear Reactor Core

The present work investigates an appropriate way to calculate the 1700 atomic density changes in the reactor operations. To automate this procedure, a computer program has been designed by C#. This program suggests a way to solve this problem which is based on the solution system of differential equations (Bitman) that it is designed according to Runge-Kutta Fehlberg method. The designed softwa...

Nuclear Reactor Steam Generation

1. Steam Generation 1.1. General Characteristics 1.2. Circulation in Boiling Water Reactors 1.3. Steam Generation in CANDU Reactors 1.4. Steam Generators 1.5. Steam Generator for PWR and CANDU Systems 1.6. Heat Transfer 2. Steam Generator Operation 2.1. Swelling and Shrinking 2.1.1. Steady State Swelling and Shrinking 2.1.2. Transient Swelling and Shrinking 2.2. Level Control 2.3. Carryover 2.4...

Nuclear Reactor Kinetics

1. Reactor Kinetics 1.

Nuclear Reactor Hazards

Examination of reactor grade graphite using neutron powder diffraction

Graphite is of principal interest in Generation IV nuclear reactor concepts. In particular, graphite will be the moderator for the Very High Temperature Reactor. In support of experimental and computational investigations that aim at understanding the behavior of reactor grade graphite under operating conditions, neutron powder diffraction experiments have been performed at the North Carolina S...