239Pu evaluation comparison study-Reference-Cited by-同舟云学术

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239Pu evaluation comparison study

Published:2018-08 Issue: Volume:118 Page:313-316
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Alrwashdeh Mohammad

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. Covariance data evaluation for 233U;Alrwashdeh;Appl. Radiat. Isot.,2017

2. Development of a code FITWR for nuclear cross section statistical analysis;Alrwashdeh;Ann. Nucl. Energy,2014

3. U233 Data evaluation for criticality study;Alrwashdeh;J. Nucl. Eng. Radiat. Sci.,2016

4. Nuclear Cross Section Statistical Analysis with FITWR Program;Alrwashdeh;Energy Dev. Front.,2013

5. Nuclear data statistical treatment;Alrwashdeh,2013

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1. Evaluation of Neutron Cross-Section Data Using Gaussian Mixture Model and Digital Filter;Nuclear Science and Engineering;2023-10-19

2. Sensitivity neutronic analysis of accident tolerant fuel concepts in APR1400;Journal of Nuclear Materials;2023-08

3. A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design;Arabian Journal for Science and Engineering;2023-05-08

4. Research of spallation reaction on plutonium target irradiated by protons with energy of 660 MeV;Scientific Herald of Uzhhorod University Series Physics;2022-11-23

5. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core;Energies;2022-10-28

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