KR840000944A

KR840000944A - Manual stop of pressurized water reactor

Info

Publication number: KR840000944A
Application number: KR1019820002496A
Authority: KR
Inventors: 도날드 뮤직 찰스
Original assignee: 엘던 에이취. 루더; 컴버스쳔 엔지니어링, 인코퍼레이티드
Priority date: 1981-07-07
Filing date: 1982-06-03
Publication date: 1984-03-26
Also published as: JPS5818200A

Abstract

내용 없음No content

Description

Manual stop of pressurized water reactor

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음As this is a public information case, the full text was not included.

제1도는 가압경수로형 원자로의 핵 증기 공급 시스템에 대한 계통도. 제2도는 원자로 냉각제 시스템에 대한 가압기의 관계를 그린 계통도.1 is a schematic diagram of a nuclear steam supply system for a PWR reactor. 2 is a schematic diagram of the pressurizer's relationship to the reactor coolant system.

Claims

A reactor cooling system having a reactor, an on lag pipe connecting the reactor outlet to the steam generator, a cold lag pipe connecting the steam generator to the reactor inlet, pumping means for circulating the primary coolant through the reactor cooling system, and In a pressurized water reactor reactor supply system comprising a pressurizer which is normally operated to have an upper region filled with steam by contacting a lower region filled with water and communicating fluid through a sudden increase in on-lag piping.

An improved pressurizer is placed in the upper region for manually transferring the rapidly increasing coolant from the reactor cooling system and for discharging the increased coolant into the upper region of the pressurizer, whereby a portion of the reactor coolant is vaporized in the upper region. And a conduit means mixed with the pressurized water reactor.

The improved pressurizer of claim 1, wherein the conduit means consists of a vertically arranged tube having an open end in the lower region filled with liquid and another open end in the upper region filled with steam, and fixed and supported in the press. Pressurized water reactor reactor.

3. The pressurized water reactor of claim 1, wherein the means for discharging comprises means for injecting the discharged water into a steam filled upper region.

On lag piping connecting the reactor outlet to a steam generator in heat transfer relationship, in turn with the J cooling loop, a cold lag piping connecting the steam generator to the reactor inlet, and means for circulating primary coolant through the reactor cooling system. A primary coolant system consisting of: a reactor having a negative retarder temperature response coefficient at which the reactor power is essentially enhanced to an extinction heat level at the peak value of the average primary coolant above the power rating; A pressurized water reactor-type nuclear steam supply system including a pressurizer in fluid communication with the on-lag pipe, wherein the pressurizer has a upper region filled with steam in contact with a lower region filled with a liquid and corresponds to the peak temperature. Increasing the volume of the vapor at A pressurized light-water reactor type reactor characterized in that the scale is acceptable to the pressurizer without collapse.

In the improved pressurizer of claim 6, the steam is produced through the duration of any transition period in which the average peak temperature of the primary coolant occurs as a result of heat generated in the reactor larger than the heat from which the pressurizer is transferred to the secondary loop through the steam generator. And a scale such that the liquid can remain saturated there.

※ Note: The disclosure is based on the initial application.