NUCLEAR REACTOR SAFETY AEROSOLS

CSNI Specialist Meeting on Nuclear Aerosols in Reactor Safety

This paper gives the perspective on fission product behavior and source term research of the Project Nuclear Safety (PNS) at the Karlsruhe Nuclear Research Center (KfK). It tries to demonstrate the conceptional background of the KfK core melting program, which has been started in 1973, and which is scheduled to be terminated by 1986. The paper also summarizes the main findings of the SASCHA pro...

Safety Aspects of Nuclear Reactor Control

Reactor control and safety systems are discussed with emphasis on safety considerations. Consideration is given to the importance of reactor characteristics, control and safety system characteristics, the operational program of the reactor, and credible accidents, in a determination of safety of operation. Ecperience with research reactor control and safety systems has led to the development of...

Assessment of Cfd Codes Used in Nuclear Reactor Safety Simulations

The spectacular growth in computer hardware over the last quarter century and the accompanying advances in software development have resulted in the availability of reliable numerical tools for addressing safety issues in Nuclear Power Plants (NPPs). The first step forward was undertaken in the 1970s with the development of system codes using the two-fluid model approach [1], such as RELAP-5 [2...

Computational Fluid Dynamics for Nuclear Reactor Safety-5 (CFD4NRS-5)

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...