The patent badge is an abbreviated version of the USPTO patent document. The patent badge does contain a link to the full patent document.
The patent badge is an abbreviated version of the USPTO patent document. The patent badge covers the following: Patent number, Date patent was issued, Date patent was filed, Title of the patent, Applicant, Inventor, Assignee, Attorney firm, Primary examiner, Assistant examiner, CPCs, and Abstract. The patent badge does contain a link to the full patent document (in Adobe Acrobat format, aka pdf). To download or print any patent click here.
Patent No.:
Date of Patent:
May. 18, 1993
Filed:
Nov. 20, 1990
Shigeo Hatamiya, Hitachi, JP;
Masanori Naitoh, Hitachi, JP;
Yoshiyuki Kataoka, Ibaraki, JP;
Hiroaki Suzuki, Hitachi, JP;
Isao Sumida, Ibaraki, JP;
Toshitsugu Nakao, Hitachi, JP;
Kanehiro Ochiai, Hitachi, JP;
Tsuyoshi Niino, Hitachi, JP;
Masataka Hidaka, Hitachi, JP;
Tohru Fukui, Hitachi, JP;
Ryuhei Kawabe, Hitachi, JP;
Hitachi, Ltd., Tokyo, JP;
Abstract
A pressure control chamber of a reactor containment vessel for receiving the atmosphere of the reactor containment vessel containing leakage steam developing in the event of an accident includes a pressure control pool, and a wet well disposed above the pressure control pool. The wet well is divided into an inner peripheral portion and an outer peripheral portion. The inner and outer peripheral portions are communicated with each other via the pressure control pool. An outlet port for flowing the atmosphere of the reactor containment vessel containing the leakage steam is provided at the inner peripheral side of the pressure control pool. When the atmosphere of the reactor containment vessel containing the leakage steam is introduced into the pressure control pool in the event of the accident, this atmosphere is condensed by the water in the pressure control pool, and the gas of this atmosphere not condensed is accumulated in the inner peripheral portion of the wet well. As a result, the pressure within the inner peripheral portion is increased to increase the water level of the pressure control pool at the outer peripheral portion, so that the area of contact of a reactor containment vessel wall with the pressure control pool water is increased, thereby enhancing a heat radiation performance of the reactor containment vessel.