Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly-Reference-Cited by-同舟云学术

Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly

Published:2021-12 Issue: Volume:384 Page:111486
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Alrwashdeh Mohammad^ORCID,Alameri Saeed A.^ORCID

Funder

United Arab Emirates Ministry of Higher Education and Scientific Research

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference31 articles.

1. Neutronic and Fuel Performance Evaluation of Accident Tolerant Fuel Concepts in APR1400 Reactor;Alnoamani;Transactions,2018

2. 239Pu evaluation comparison study;Alrwashdeh;Ann. Nucl. Energy,2018

3. Covariance data evaluation for 233U;Alrwashdeh;Appl. Radiat. Isot.,2018

4. Homogenization of TRISO Fuel using Reactivity Equivalent Physical Transformation Method;Alrwashdeh;Transactions,2019

5. Evaluation review of the 250Cf neutron cross section;Alrwashdeh;Appl. Radiat. Isot.,2019

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