Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions-Reference-Cited by-同舟云学术

登录注册会员服务联系我们

Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions

Published:2024-08 Issue: Volume:203 Page:110503
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Ederli Stefano,Drai Patrick,Obada Dorel,Girault Nathalie,Mascari Fulvio

Funder

H2020 Euratom

Publisher

Elsevier BV

Reference25 articles.

1. Bradt, P. Review of the radiological consequences evaluation methodologies, R2CA internal report, March 2021.

2. Chailan, L., et al, Overview of the ASTEC code and models for evaluation of Severe Accidents in Water Cooled Reactors, IAEA Technical meeting on the Status and evaluation of Severe Accidents simulation codes for Water Cooled Reactors, Vienna (Austria), October 2017, 9-12.

3. “Multi-rod burst test”, program Progress report april-june 1979 USNRC report – ORNL/NUREG/CR-1023;Chapman,1979

4. Main modelling features of ASTEC v2.1 major version;Chatelard;Ann. Nucl. Energy,2016

5. D40.45 – set of final” reference” NPP ASTEC input decks;Chatelard;Report of EU-CESAM Project,2017

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线，采集、加工和组织学术论文而形成的新型学术文献查询和分析系统，可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容，当前同舟云学术共收录了国内外主流学术期刊6万余种，收集的期刊论文及会议论文总量共计约1.5亿篇，并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询！咨询电话：010-8811{复制后删除}0370

www.globalauthorid.com

TOP