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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2009.1
- 수록면
- 765 - 774 (10page)
이용수
초록· 키워드
오류제보하기
For over 30 years, investigations of the thermohydraulic behavior of pressurized-water reactors under accident conditions
have been carried out in the PKL test facility at AREVA NP in Erlangen, Germany. The PKL facility models the entire
primary side and significant parts of the secondary side of a of pressurized water reactor at a height scale of 1:1. Volumes,
power ratings and mass flows are scaled with a ratio of 1:145. The experimental facility consists of four primary loops with
circulation pumps and steam generators (SGs) arranged symmetrically around the reactor pressure vessel (RPV). The
investigations carried out encompass a very broad spectrum from accident scenario simulations with large, medium, and
small breaks, over the investigation of shutdown procedures after a wide variety of accidents, to the systematic investigation
of complex thermohydraulic phenomena.
The PKL tests began in the mid 1970s with the support of the German Research Ministry. Since the mid 1980s, the project
has also been significantly supported by the German PWR operators. Since 2001, 25 partner organizations from 15 countries
have taken part in the PKL investigations with the support and mediation of the OECD/ NEA (Nuclear Energy Agency).
After an overview of PKL history and a short description of the facility, this paper focuses on the investigations carried
out since the beginning of the international cooperation, and shows, by means of some examples, what insights can be derived
from the tests.
목차
등록된 정보가 없습니다.
참고문헌 (10)
참고문헌 신청
A. Bucalossi / 2005 / Validation of Thermal-Hydraulic Codes for Boron Dilution Transients in the Context of the OECD/SETH Project / Seminar 2
J. Hyvarinen / 1993 / The inherent boron dilution mechanism in pressurized water reactors / Nuclear Engineering and Design 145 : 227 ~ 240
J. Liebert / 1999 / Results of UPTF and PKL Research Projects for PWR Plant Operation / VGB PowerTech 8 : 20 ~ 27
K. Umminger / 2003 / Experiments on Boron Dilution in the Integral Test Facility / PKL Nureth 10
K. Umminger / 2006 / KL Experiments on Loss of Residual Heat Removal under Shutdown Conditions in PWRs / 2006 International Congress on Advances in Nuclear Power Plants (ICAPP ’06
J. Hyvarinen / 1993 / The inherent boron dilution mechanism in pressurized water reactors / Nuclear Engineering and Design 145 : 227 ~ 240
J. Liebert / 1999 / Results of UPTF and PKL Research Projects for PWR Plant Operation / VGB PowerTech 8 : 20 ~ 27
K. Umminger / 2003 / Experiments on Boron Dilution in the Integral Test Facility / PKL Nureth 10
K. Umminger / 2006 / KL Experiments on Loss of Residual Heat Removal under Shutdown Conditions in PWRs / 2006 International Congress on Advances in Nuclear Power Plants (ICAPP ’06
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