A Versatile Methodology for Reactor Pressure Vessel Aging Assessments-Reference-Cited by-同舟云学术

A Versatile Methodology for Reactor Pressure Vessel Aging Assessments

Published:2021-11-29 Issue: Volume: Page:1-23
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Vuiart Romain¹^ORCID,Brovchenko Mariya¹,Taforeau Julien¹,Jaiswal Vaibhav¹,Dumonteil Eric²

Affiliation:

1. Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Fontenay-aux-Roses 92260, France

2. Commissariat à l’énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur les lois Fondamentales de l’Univers (IRFU), Gif-sur-Yvette 91190, France

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2021.1991761

Reference38 articles.

1. “Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels,” Nuclear Energy Series, NP-T-3.11, International Atomic Energy Agency (2009).

2. Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence

3. Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data

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