Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Xinghe Ni"'
Autor:
M. Adorni, Christine Bals, Sara Beck, S. Bernaud, A. Boulore, N. Chauvin, Hui Cheng, Ryan Dailey, A. Del Nevo, Xiaomeng Dong, Guangtao Duan, J.C. Dumas, A. Duncan, Tangtao Feng, Miao Gui, Anil Gurgen, T. Helfer, Thorsten Hollands, C. Introini, Seiichi Koshizuka, M. Lainet, Xin Li, Lianshan Lin, Liviusz Lovasz, L. Luzzi, A. Magni, V. Marelle, R. Masson, B. Michel, Kaya G. Mondry, Xinghe Ni, L. Noirot, Holger Nowack, Marco Pellegrini, Alejandro Perez, Bowen Qiu, I. Ramière, D. Rozzia, Shimpei Saito, Andreas Schaffrath, A. Schubert, J. Sercombe, Martin Sonnenkalb, Claus Spengler, Guanghui Su, Lin Sun, Z.J. Sun, P. Van Uffelen, George Vayssier, I. Viallard, Jun Wang, Xing Wang, Zidi Wang, Andreas Wielenberg, Jianqi Xi, Akifumi Yamaji, Jiankai Yu, Fan Zhang, Jing Zhang, Luteng Zhang, Tengfei Zhang, Xingang Zhao, Xianping Zhong, Yukun Zhou
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6dac0597818b4fd17877da9303ddcafa
https://doi.org/10.1016/b978-0-12-818190-4.00028-0
https://doi.org/10.1016/b978-0-12-818190-4.00028-0
Autor:
Xinghe Ni
Publikováno v:
Nuclear Power Plant Design and Analysis Codes ISBN: 9780128181904
This chapter is not intending to delve into specific techniques but rather to deliver a brief overview of software quality assurance (SQA) for nuclear power engineering software. Before studying how to assure software quality, people should know that
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::117d2e459899bc0c04e12d62b27176e7
https://doi.org/10.1016/b978-0-12-818190-4.00003-6
https://doi.org/10.1016/b978-0-12-818190-4.00003-6
Publikováno v:
Progress in Nuclear Energy. 103:191-208
It is important to predict the hydrogen generated from cladding oxidation under severe accident conditions. The processes of high and ultrahigh temperature oxidation with cladding damaged are complicated and the accurate simulation models need to be
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e7bf341e719024f6c732c76c2a5a2d53
https://doi.org/10.1016/j.pnucene.2017.11.020
https://doi.org/10.1016/j.pnucene.2017.11.020
Publikováno v:
Nuclear Engineering and Design. 326:244-260
The prediction of hydrogen generated from fuel cladding by steam oxidation is significant in severe accident analysis. However, the existing methods and models are difficult to make an accurate prediction of hydrogen generation rate for integrated ex
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a1392fe7c83101bd90931e445ef6f6b7
https://doi.org/10.1016/j.nucengdes.2017.11.012
https://doi.org/10.1016/j.nucengdes.2017.11.012
Publikováno v:
Progress in Nuclear Energy. 93:47-58
In this study, the radioactivity of noble gases during loss of coolant accidents in containment is simulated by using CPR1000 nuclear power plant simulator in Ningde Fujian China. A simple fission product release model along with two real-time simula
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3d240d8ba58f38313d9a4b53857a0e96
https://doi.org/10.1016/j.pnucene.2016.07.019
https://doi.org/10.1016/j.pnucene.2016.07.019
Autor:
Michael L. Corradini, Yuqiao Fan, Guanghui Su, Jun Wang, Xinghe Ni, Wenxi Tian, Yapei Zhang, Suizheng Qiu
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 2
The occurrence of Fukushima has increased the focus on the development of severe accident codes and their applications. As a part of Chinese “National Major Projects,” a module in-vessel degraded analysis code (MIDAC) is currently being developed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8091148375d60438ed10ec72cd270d21
https://doi.org/10.1115/1.4031842
https://doi.org/10.1115/1.4031842