Evaluation of the Loss of Residual Heat Removal Systems in Pressurized Water Reactors with U-Tube Steam Generators

An investigation on the thermal hydraulic characteristics of the passive residual heat removal system (PRHRS) which is used in an integral pressurized water reactor (INSURE-100) is presented in this paper. The main components of primary coolant system are enclosed in reactor vessel. Primary fluid flow circle is natural circulation. The PRHRS can remove the energy from the primary side as long as the residual heat exchanger (RHE) is submerged in the emergency cooldown tank (ECT). The parameter study is performed by considering the effects of an effective height between the steam generators and the RHE and a valve actuation time, which are useful for the design of the PRHRS. The mass flow in the PRHRS has been affected by the height difference between the steam generators and the RHE. The pressure peak of the primary side and PRHRS has been affected by the valve action time.

Download Full-text

Entfernung eisenoxidhaltiger Beläge aus Dampferzeugern von Druckwasserreaktoren / Removal of deposits containing iron oxide from steam generators of pressurized water reactors

Kerntechnik ◽

10.1515/kern-1993-580115 ◽

1993 ◽

Vol 58 (1) ◽

pp. 37-39

Author(s):

J. Bosholm

Keyword(s):

Iron Oxide ◽

Pressurized Water Reactors ◽

Steam Generators ◽

Pressurized Water ◽

Water Reactors

Download Full-text

Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)

Kerntechnik ◽

10.1515/kern-2020-850108 ◽

2020 ◽

Vol 85 (1) ◽

pp. 54-67

Author(s):

A. Hamedani ◽

O. Noori-Kalkhoran ◽

R. Ahangari ◽

M. Gei

Keyword(s):

Steam Generator ◽

Nuclear Power ◽

Axial Direction ◽

Pressurized Water Reactors ◽

Steam Generators ◽

Pressurized Water ◽

Heated Channel ◽

Water Reactors ◽

Secondary Side

Abstract Steam generators are one of the most important components of pressurized-water reactors. This component plays the role of heat transfer and pressure boundary between primary and secondary side fluids. The Once Through Steam Generator (OTSG) is an essential component of the integrated nuclear power system. In this paper, steady-state analysis of primary and secondary fluids in the Integral Economizer Once Through Steam Generator (IEOTSG) have been presented by Single Heated Channel (SHC) and subchannel modelling. Models have been programmed by MATLAB and FORTRAN. First, SHC model has been used for this purpose (changes are considered only in the axial direction in this model). Second, the subchannel approach that considers changes in the axial and also radial directions has been applied. Results have been compared with Babcock and Wilcox (B&W) 19- tube once through steam generator experimental data. Thermal- hydraulic profiles have been presented for steam generator using both of models. Accuracy and simplicity of SHC model and importance of localization of thermal-hydraulic profiles in subchannel approach have been proved.

Download Full-text