[특허]Method of uprating an existing nuclear power plant

Westinghouse Electric Company LLC

검색어에 아래의 연산자를 사용하시면 더 정확한 검색결과를 얻을 수 있습니다.
검색연산자

검색도움말
검색연산자	기능	검색시 예
()	우선순위가 가장 높은 연산자	예1) (나노 (기계 \| machine))
공백	두 개의 검색어(식)을 모두 포함하고 있는 문서 검색	예1) (나노 기계) 예2) 나노 장영실
\|	두 개의 검색어(식) 중 하나 이상 포함하고 있는 문서 검색	예1) (줄기세포 \| 면역) 예2) 줄기세포 \| 장영실
!	NOT 이후에 있는 검색어가 포함된 문서는 제외	예1) (황금 !백금) 예2) !image
*	검색어의 *란에 0개 이상의 임의의 문자가 포함된 문서 검색	예) semi*
""	따옴표 내의 구문과 완전히 일치하는 문서만 검색	예) "Transform and Quantization"

과학기술 지식인프라 ScienceON

연합인증

연합인증 가입 기관의 연구자들은 소속기관의 인증정보(ID와 암호)를 이용해 다른 대학, 연구기관, 서비스 공급자의 다양한 온라인 자원과 연구 데이터를 이용할 수 있습니다.

이는 여행자가 자국에서 발행 받은 여권으로 세계 각국을 자유롭게 여행할 수 있는 것과 같습니다.

연합인증으로 이용이 가능한 서비스는 NTIS, DataON, Edison 등이 있습니다.

한번의 인증절차만으로 연합인증 가입 서비스에 추가 로그인 없이 이용이 가능합니다.

다만, 연합인증을 위해서는 최초 1회만 인증 절차가 필요합니다. (회원이 아닐 경우 회원 가입이 필요합니다.)

연합인증 절차는 다음과 같습니다.

최초이용시에는
ScienceON에 로그인 → 연합인증 서비스 접속 → 로그인 (본인 확인 또는 회원가입) → 서비스 이용

그 이후에는
ScienceON 로그인 → 연합인증 서비스 접속 → 서비스 이용

연합인증을 활용하시면 KISTI가 제공하는 다양한 서비스를 편리하게 이용하실 수 있습니다.

특허 상세정보

MyON담기

내보내기 페이스북 공유 트위터 공유 카카오톡 공유

Method of uprating an existing nuclear power plant

특허상세정보
국가/구분	United States(US) Patent 등록
국제특허분류(IPC7판)	G21C-001/01
미국특허분류(USC)	376/260; 376/210; 376/211; 376/212; 376/261; 376/241; 376/267; 376/402
출원번호	US-0356950 (2003-02-03)
발명자 / 주소	Lahoda, Edward J.
출원인 / 주소	Westinghouse Electric Company LLC
인용정보	피인용 횟수 : 14 인용 특허 : 8

초록
▼

An improved method of increasing the power output of an existing nuclear power plant includes increasing the thermal power output of the plant's nuclear island and constructing of an auxiliary BOP to handle the increased thermal power. The thermal power of the nuclear island can be increased such as by increasing the thermal power of the plant's reactor, by replacing the plant's steam generator with one that is more efficient, and by increasing the flow rate and/or change in temperature of a coolant in a secondary cooling loop of the plant. The thermal power of the reactor can be increased such as by replacing existing cylindrical fuel rods with fuel rods having a relatively greater surface area to volume ratio and/or by increasing the flow rate and/or the change in temperature of a coolant of a primary cooling loop. The auxiliary BOP can be constructed while the plant is in operation, and can then be connected with the nuclear island during a maintenance operation on the reactor.

대표
청구항
▼

1. A method of increasing the electrical power output of an existing nuclear power plant, the plant including a nuclear island and a balance of plant connected together, the nuclear island including a containment having an interior, a pressurized water reactor having a number of fuel rods that include fissile material, and a steam generator, the reactor and the steam generator being disposed within the interior of the containment, the containment outputting thermal power, and the balance of plant outputting electrical power, the method comprising:operating the nuclear island during a first time period to output from the containment thermal power at a first rate: constructing an auxiliary balance of plant, at least a portion of said constructing an auxiliary balance of plant occurring during at least a portion of the first time period while the nuclear island is operating; connecting the auxiliary balance of plant with the nuclear island; increasing the thermal power output from the containment by operating the nuclear island during a second time period substantially subsequent to connection of the auxiliary balance of plant with the nuclear island to output from the containment thermal power at a second rate that is relatively greater than the first rate; delivering a portion of the thermal power to the auxiliary balance of plant; and outputting electrical power from the auxiliary balance of plant. 2. The method as set forth in claim 1, in whichthe reactor outputs thermal power; said increasing the thermal power output from the containment including; operating the reactor to output thermal power at a first rate; and increasing the thermal power output of the reactor by subsequently operating the reactor to output thermal power at a second, relatively higher rate. 3. The method as set forth in claim 2, in whichthe fuel rods have a surface area to volume ratio; said increasing the thermal power output of the reactor including increasing the surface area to volume ratio of the fuel rods by replacing at least a portion of the fuel rods with alternate fuel rods having a relatively higher surface area to volume ratio. 4. The method as set forth in claim 3, in whichthe fuel rods include cylindrical fuel rods; and said increasing the surface area to volume ratio of the fuel rods includes replacing the cylindrical fuel rods with annular fuel rods. 5. The method as set forth in claim 4, in whichsaid replacing the cylindrical fuel rods with annular fuel rods includes replacing the cylindrical fuel rods with annular fuel rods having an annular cladding within which is disposed fissile material. 6. The method as set forth in claim 3, in whichsaid increasing the thermal power output of the reactor includes installing neutron reflectors within the containment. 7. The method as set forth in claim 3, further comprising increasing the quantity of fissile material in the fuel rods.8. The method as set forth in claim 7, in which said increasing the quantity of fissile material in the fuel rods includes at least one of:replacing the fuel rods with other fuel rods that are relatively longer; installing neutron reflectors to increase the efficiency of neutron usage; replacing the fissile material with other fissile material having a lower neutron cross section; increasing the concentration of the fissile material compared with non-fissile material in the fuel rods; and increasing the density of the fissile material in order to accommodate more fissile material in the fuel rods. 9. The method as set forth in claim 2, in whichthe steam generator is a square-pitch steam generator; said increasing the thermal power output from the containment including replacing the square-pitch steam generator with a triangular-pitch steam generator. 10. The method as set forth in claim 1, in whichthe reactor outputs thermal power and includes a primary cooling loop carrying a primary coolant; the plant including a secondary cooling loop carrying a secondary coolant and being connected with the balance of plant and the auxiliary balance of plant; the steam generator thermally connecting together the primary and secondary cooling loops; said increasing the thermal power output from the containment including at least one of: increasing the thermal power output of the reactor; increasing the flow rate of the primary coolant; increasing the change in temperature of the primary coolant flowing through the steam generator; increasing the change in temperature of the primary coolant flowing through the reactor; increasing the flow rate of the secondary coolant; increasing the change in temperature of the secondary coolant flowing through the steam generator; and increasing the thermal efficiency of the steam generator. 11. The method as set forth in claim 1, further comprising:connecting the auxiliary balance of plant with the containment contemporaneously with the performance of a maintenance operation on the reactor. 12. The method as set forth in claim 11, further comprising:at least partially building the auxiliary balance of plant prior to initiating the maintenance operation on the reactor. 13. The method as set forth in claim 12, further comprising:at least partially building the auxiliary balance of plant while the power plant is operating. 14. The method as set forth in claim 1, further comprising:ceasing to generate electrical power from the balance of plant. 15. A method of increasing the electrical power output of an existing nuclear power plant substantially without a need of altering a containment of the plant, the plant including a nuclear island and a balance of plant connected together, the nuclear island including the containment which includes an interior, a pressurized water reactor having a number of fuel rods that include fissile material, and a steam generator, the or and the steam generator being disposed within the interior of the containment, the reactor outputting thermal power, and the balance of plant outputting electrical power, the method comprising:operating the nuclear island during a first time period to output from the reactor thermal power at a first rate; constructing an auxiliary balance of plant at least constructing an auxiliary balance of plant occurring during at least a portion of the first time period while the nuclear island is operating; thermally connecting the auxiliary balance of plant with the reactor; increasing the thermal power output from the containment by operating the nuclear island during a second time period substantially subsequent to connection of the auxiliary balance of plant with the reactor to output from the reactor thermal power at a second rate that is relatively greater than the first rate; and outputting electrical power from the auxiliary balance of plant. 16. The method as set forth in claim 15, in whichthe fuel rods have a surface area to volume ratio; said increasing the thermal power output of the reactor including increasing the surface area to volume ratio of the fuel rods by replacing at least a portion of the fuel rods with alternate fuel rods having a relatively higher surface area to volume ratio. 17. The method as set forth in claim 16, in whichthe fuel rods include cylindrical fuel rods; and said increasing the surface area to volume ratio of the fuel rods includes replacing the cylindrical fuel rods with annular fuel rods. 18. The method as set forth in claim 17, in whichsaid replacing the cylindrical fuel rods with annular fuel rods includes replacing the cylindrical fuel rods with annular fuel rods having an annular cladding within which is disposed fissile material. 19. The method as set forth in claim 15, further comprisingincreasing the quantity of fissile material in the fuel rods. 20. The method as set forth in claim 19, in whichsaid increasing the quantity of fissile material in the fuel rods includes least one of: replacing the fuel rods with other fuel rods that are relatively longer; installing neutron reflectors to increase the efficiency of neutron usage; replacing the fissile material with other fissile material having a lower neutron cross section; increasing the concentration of the fissile material compared with non-fissile material in the fuel rods; and increasing the density of the fissile material in order to accommodate more fissile material in the fuel rods. 21. The method as set forth in claim 15, in whichthe reactor includes a primary cooling loop crying a primary coolant; the plant including a secondary cooling loop carrying a secondary coolant and being connected with the balance of plant and the auxiliary balance of plant; the steam generator thermally connecting together the primary and secondary cooling loops; the method further comprising at least one of: increasing the flow rate of the primary coolant; increasing the change in temperature of the primary coolant flowing through the steam generator; increasing the change in temperature of the primary coolant flowing through the reactor; increasing the flow rate of the secondary coolant; increasing the change in temperature of the secondary coolant flowing through the steam generator; and increasing the thermal efficiency of the steam generator. 22. The method as set forth in claim 15, further comprising:connecting the auxiliary balance of plant with the containment during a scheduled shutdown of the reactor for the performance of a maintenance operation on reactor. 23. The method as set forth in claim 22, further comprising:at least partially building the auxiliary balance of plant prior to initiating the shutdown of the reactor. 24. The method as set forth in claim 23, further comprising:at least partially building the auxiliary balance of plant while the power plant is operating. 25. The method as set forth in claim 15, further comprising:modifying the reactor to increase the thermal power output thereof substantially without altering the volume occupied by the reactor; and replacing the steam generator to increase the efficiency thereof substantially without altering the volume occupied by the steam generator. 26. The method as set forth in claim 15, further comprising:ceasing to generate electrical power from the balance of plant.

이 특허에 인용된 특허 (8)

이 특허를 인용한 특허 (14)

IPC 상위 출원인

내보내기

상세정보
내보내기 구분	파일저장 인쇄 메일전송
구성항목	관리번호, 국가코드, 자료구분, 상태, 출원번호, 출원일자, 공개번호, 공개일자, 등록번호, 등록일자, 발명명칭(한글), 발명명칭(영문), 출원인(한글), 출원인(영문), 출원인코드, 대표IPC 관리번호, 국가코드, 자료구분, 상태, 출원번호, 출원일자, 공개번호, 공개일자, 공고번호, 공고일자, 등록번호, 등록일자, 발명명칭(한글), 발명명칭(영문), 출원인(한글), 출원인(영문), 출원인코드, 대표출원인, 출원인국적, 출원인주소, 발명자, 발명자E, 발명자코드, 발명자주소, 발명자 우편번호, 발명자국적, 대표IPC, IPC코드, 요약, 미국특허분류, 대리인주소, 대리인코드, 대리인(한글), 대리인(영문), 국제공개일자, 국제공개번호, 국제출원일자, 국제출원번호, 우선권, 우선권주장일, 우선권국가, 우선권출원번호, 원출원일자, 원출원번호, 지정국, Citing Patents, Cited Patents
저장형식	Text(ASCII format) Excel format PIAS분석(.xls)
메일정보	받는사람 (필수) @ 보내는사람 (선택) @ 제목 내용 KISTI 검색결과 이메일 서비스
안내	> 총 건의 자료가 검색되었습니다. > 다운받으실 자료의 인덱스를 입력하세요. (1-10,000) > 검색결과의 순서대로 최대 10,000건 까지 다운로드가 가능합니다. > 데이타가 많을 경우 속도가 느려질 수 있습니다.(최대 2~3분 소요) > 다운로드 파일은 UTF-8 형태로 저장됩니다. 파일의 내용이 제대로 보이지 않을실 때는 웹브라우저 상단의 보기 -> 인코딩 -> 자동선택 여부를 확인하십시오 > ~ > Text(ASCII format) Excel format

과학기술 지식인프라 ScienceON

ScienceON Chatbot

연합인증

특허 상세정보

Method of uprating an existing nuclear power plant

초록
▼

대표
청구항
▼

이 특허에 인용된 특허 (8)

이 특허를 인용한 특허 (14)

IPC 상위 출원인

과제정보

상세정보조회

원문조회

IPC 상세정보(version : 201201)

연구과제 성과물(0)

참여연구원의 다른 문헌(0)

처리중입니다.

잠시만 기다려주세요.

ScienceON Chatbot

연합인증

특허 상세정보

Method of uprating an existing nuclear power plant

초록 ▼

대표청구항 ▼

이 특허에 인용된 특허 (8)

이 특허를 인용한 특허 (14)

IPC 상위 출원인

과제정보

상세정보조회

원문조회

IPC 상세정보(version : 201201)

연구과제 성과물(0)

참여연구원의 다른 문헌(0)

처리중입니다.

잠시만 기다려주세요.

초록
▼

대표
청구항
▼