The Models Used in Predicting Steam Condensation Occurs during Nuclear Reactor Loss of Coolant Accident

Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions

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...

the effect of e-64 on the developmental competence of sheep cocs during in vitro maturation

in the present study, the effect of e-64 at different concentrations (0.5, 1, 5 and 10 µm) added to (1) the ivm medium on oocyte nuclear maturation and developmental competence of ovine oocytes, and (2) to the ivc medium on embryonic development of ovine embryos were investigated.

Nuclear fuel in a reactor accident.

Nuclear accidents that lead to melting of a reactor core create heterogeneous materials containing hundreds of radionuclides, many with short half-lives. The long-lived fission products and transuranium elements within damaged fuel remain a concern for millennia. Currently, accurate fundamental models for the prediction of release rates of radionuclides from fuel, especially in contact with wat...

Evaluation of Single Failure Effects During Loss of Coolant Accidents For A VVER-440 Reactor

This paper describes the results of an analysis of loss of coolant accidents (LOCA's) for the Soviet designed, light water cooled and moderated reactors referred to as VVERs. The VVER unit selected for this analysis is designated as VvER-440 Model 213. This plant generates 440 Mwe and is of current interest since meen are now operating and additional units are in various stages of construction ...