Author/Creator: Aziz, Moustafa - British Library Electronic Legal Deposit Catalogue-Journal Issues and Articles Search Results

Author/Creator Aziz, Moustafa

1. Analysis of thorium fuel feasibility in large scale gas cooled fast reactor using MCNPX code. (January 2018)

Authors:: Ibrahim, Amr; Aziz, Moustafa; EL-Kameesy, S.U.; EL-Fiki, S.A.; Galahom, A.A.
Journal:: Annals of nuclear energy
Issue:: Volume 111(2018)
Page Start:: 460
Record Type:: Journal Article
View Content:: Available online (eLD content is only available in our Reading Rooms) ↗

2. Comparative neutronic study for heterogeneous and homogeneous fuel assembly in a lead-cooled fast reactor. Issue 1 (July 2021)

Authors:: Ibrahim, Mohammed; Ibrahim, Amr; Aziz, Moustafa; Saudi, H A; Hassaan, M Y
Journal:: IOP conference series
Issue:: Volume 1171:Issue 1(2021)
Page Start:
Record Type:: Journal Article
View Content:: Available online (eLD content is only available in our Reading Rooms) ↗

3. Design of an MCNPX model to simulate the performance of BWRs using thorium as fuel and its validation with HELIOS code. (March 2015)

Authors:: Abdelghafar Galahom, A.; Bashter, I.I.; Aziz, Moustafa
Journal:: Annals of nuclear energy
Issue:: Volume 77(2015:Mar.)
Page Start:: 393
Record Type:: Journal Article
View Content:: Available online (eLD content is only available in our Reading Rooms) ↗

4. Design of an MCNPX model to simulate the performance of BWRs using thorium as fuel and its validation with HELIOS code. (March 2015)

Authors:: Abdelghafar Galahom, A.; Bashter, I.I.; Aziz, Moustafa
Journal:: Annals of nuclear energy
Issue:: Volume 77(2015:Mar.)
Page Start:: 393
Record Type:: Journal Article
View Content:: Available online (eLD content is only available in our Reading Rooms) ↗

5. Neutronic analysis and validation of boiling water reactor core designed by MCNPX code. (February 2015)

Authors:: Galahom, Ahmed Abdelghafar; Bashter, I.I.; Aziz, Moustafa
Journal:: Annals of nuclear energy
Issue:: Volume 76(2015:Feb.)
Page Start:: 461
Record Type:: Journal Article
View Content:: Available online (eLD content is only available in our Reading Rooms) ↗

6. Neutronic analysis and validation of boiling water reactor core designed by MCNPX code. (February 2015)

Authors:: Galahom, Ahmed Abdelghafar; Bashter, I.I.; Aziz, Moustafa
Journal:: Annals of nuclear energy
Issue:: Volume 76(2015:Feb.)
Page Start:: 461
Record Type:: Journal Article
View Content:: Available online (eLD content is only available in our Reading Rooms) ↗

7. Searching for optimal accident tolerant fuel for the VVER-1200 reactor from the neutronic point of view. Issue 1 (31st December 2023)

Authors:: Galahom, A. Abdelghafar; Aboelyazid, Ehab M.; EL-Fiki, S.A.; Aziz, Moustafa
Journal:: Energy sources
Issue:: Volume 45:Issue 1(2023)
Page Start:: 1405
Record Type:: Journal Article
View Content:: Available online (eLD content is only available in our Reading Rooms) ↗

8. The effect of homogenization on the neutronic parameters and transmutation of GFR-2400 fast reactor fuel assembly. (December 2017)

Authors:: Ibrahim, Amr; Aziz, Moustafa; EL-Fiki, S.A.; EL-Kameesy, S.U.; Galahom, A.A.
Journal:: Annals of nuclear energy
Issue:: Volume 110(2017:Dec.)
Page Start:: 215
Record Type:: Journal Article
View Content:: Available online (eLD content is only available in our Reading Rooms) ↗