OVERVIEW ON THE DESIGN APPROACH FOR THE CVCS I & C OF THE EPR™ NUCLEAR POWER PLANT IN TAISHAN

被引：0

作者：

Ciriello, Antonio ^{[1
]}

Kohler, Daniela ^{[1
]}

Morton, Terry ^{[2
]}

Lang, Thomas ^{[1
]}

机构：

[1] AREVA GmbH, Erlangen, Germany

[2] AREVA NP Inc, Lynchburg, VA USA

来源：

PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 2 | 2014年

关键词：

D O I：

暂无

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

The I & C (Instrumentation and Control) design of the CVCS (Chemical and Volume Control System) for the EPR (TM) nuclear power plant in Taishan (TSN NPP) is shortly introduced and the corresponding I & C module assignment procedure, according to the functional safety class principle, is described An example of the I & C module assignment procedure is given for a control loop of the CVCS. In addition, the corresponding advantages and drawbacks are described and discussed The approach described introduces a new method for the concerned I & C design by improving the interface between the system, process, and I & C engineering design. In fact, a fruitful collaboration was reached between the system and I & C design for the EPR (TM) project in Taishan, for the concerned interface.

引用

页数：6

共 50 条

[31] SITE ENVELOPE APPROACH TO DOSE ASSESSMENT FOR A STANDARDIZED NUCLEAR-POWER PLANT DESIGN
DISABATINO, AA
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 521 - 521
[32] Systematic Approach to Training for the Design of Nuclear Power Plant Decommissioning Training in South Korea
Kwak, Jeong Keun
25TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2016), 2016,
[33] CRITICAL SECTION SELECTION METHODOLOGY FOR THE US EPR™ STANDARD NUCLEAR POWER PLANT
Jung, Se-Kwon
Goodman, Adam
Harrold, Joe
Alchaar, Nawar
PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 8, 2010, : 239 - 248
[34] Research and Risk Analysis of Partial Cooldown Test of EPR Nuclear Power Plant
Zeng H.
Zhao X.
Duan S.
1600, Atomic Energy Press (41): : 122 - 126
[35] UNDERGROUND NUCLEAR POWER PARKS - POWER PLANT DESIGN IMPLICATIONS
Mahar, James M.
Kunze, Jay F.
Myers, Carl W.
ICONE 16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 4, 2008, : 485 - 492
[36] LOAD COMBINATION REDUCTION METHODOLGY FOR THE US EPR™ STANDARD NUCLEAR POWER PLANT
Jung, Se-Kwon
Harrold, Joseph
Alchaar, Nawar
PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, PVP 2012, VOL 8, 2012, : 151 - 160
[37] Generation of Traction Current for the Firt Time in a Nuclear Power Plant: The Joint Nuclear Power Plant i.
Lisson, Peter
eb - Elektrische Bahnen, 1977, 48 (03): : 58 - 66
[38] DESIGN AND IMPLEMENTATION OF VISUAL DESIGN DATACENTER FOR NUCLEAR POWER PLANT
Lu Hui
Liu Zhong
Niu Bo
Zhang Lin
Rong Hui
Hu Chunping
Liu Yu
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 3, 2017,
[39] OVERVIEW OF THE NUCLEAR-POWER-PLANT STRUCTURAL INTEGRITY RESEARCH IN FINLAND
TORRONEN, K
AALTONEN, P
HANNINEN, H
MAKELA, K
KARJALAINENROIKONEN, P
KEINANEN, H
KAUPPINEN, P
RINTAMAA, R
TALJA, H
WALLIN, K
VALO, M
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1993, 55 (01) : 3 - 59
[40] Health effects of the Chernobyl nuclear power plant accident - Symposium overview
Moysich, K
Michalek, A
EPIDEMIOLOGY, 2000, 11 (04) : S160 - S160

← 1 2 3 4 5 →