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Journal Articles

Calculation of neutron flux distribution and diffusion coefficient in the slab reactor core using multi-group diffusion equation with Jacobi method

Mohammad Ali Shafii, Muldarisnur, Seni Herlina Juita Tongkukut, Artoto Arkundato

AIP Conf. Proc. 3026, 060004 (2024)

https://doi.org/10.1063/5.0199734

Published: March 2024

View article titled, Calculation of neutron flux distribution and diffusion coefficient in the slab reactor core using multi-group diffusion equation with Jacobi method

Journal Articles

Model calculation and evaluation of neutron induced reaction cross-section on 237_Np, 241_Am and 245_Cm using EMPIRE 3.2 code

Abel B. Olorunsola, Johnson A. Bamikole, Aisha A. Bello, Omolayo M. Ikumapayi, Bernard A. Adaramola

AIP Conf. Proc. 2754, 030010 (2023)

https://doi.org/10.1063/5.0161141

Published: September 2023

View article titled, Model calculation and evaluation of neutron induced reaction cross-section on 237Np, 241Am and 245Cm using EMPIRE 3.2 code

Journal Articles

Sample-induced perturbations in neutron field

Ateia W. Mahmoud, Elsayed K. Elmaghraby, Ahmed H. M. Solieman, E. Salama, A. Elghazaly, S. A. El-fiki

AIP Conf. Proc. 2620, 040001 (2023)

https://doi.org/10.1063/5.0119940

Published: March 2023

View article titled, Sample-induced perturbations in neutron field

Journal Articles

Estimation of KERMA because of neutron emission into the constituent elements of a tissue in radiotherapy

Seyed Alireza Mousavi Shirazi

AIP Conf. Proc. 2398, 020065 (2022)

https://doi.org/10.1063/5.0093397

Published: October 2022

View article titled, Estimation of KERMA because of neutron emission into the constituent elements of a tissue in radiotherapy

Journal Articles

Neutron flux distribution of slab reactor core using one-dimensional multi-group diffusion equation in the thermal energy region

Mohammad Ali Shafii, Imra Zakiya, Dian Fitriyani, Artoto Arkundato, Ade Gafar Abdullah

AIP Conf. Proc. 2663, 070007 (2022)

https://doi.org/10.1063/5.0108170

Published: September 2022

View article titled, Neutron flux distribution of slab reactor core using one-dimensional multi-group diffusion equation in the thermal energy region

Journal Articles

Feasibility study of axial compact neutron generator as SAMOP neutron source

Djoko Slamet Pudjorahardjo, Syarip, Puradwi Ismu Wahyono

AIP Conf. Proc. 2381, 020063 (2021)

https://doi.org/10.1063/5.0066258

Published: November 2021

View article titled, Feasibility study of axial compact neutron generator as SAMOP neutron source

Journal Articles

A new investigation into the estimation of transferred energy from a neutron source to a human’s body

S. A. Mousavi Shirazi

AIP Conf. Proc. 2397, 050001 (2021)

https://doi.org/10.1063/5.0063749

Published: September 2021

View article titled, A new investigation into the estimation of transferred energy from a neutron source to a human’s body

Journal Articles

Theoretical calculations involving a standard neutron yield distribution for the T-T nuclear fusion reaction

Raad Hameed Majeed, Hassan Abed Alwan

AIP Conf. Proc. 2190, 020051 (2019)

https://doi.org/10.1063/1.5138537

Published: December 2019

View article titled, Theoretical calculations involving a standard neutron yield distribution for the T-T nuclear fusion reaction

Journal Articles

Effect of boron impurity and graphite thermal neutron scattering on criticality calculation of Indonesian experimental power reactor

Suwoto, H. Adrial, W. Luthfi, T. Setiadipura, Zuhair

AIP Conf. Proc. 2180, 020002 (2019)

https://doi.org/10.1063/1.5135511

Published: December 2019

View article titled, Effect of boron impurity and graphite thermal neutron scattering on criticality calculation of Indonesian experimental power reactor

Journal Articles

Undergraduate education at the University of Kentucky accelerator laboratory

A. P. D. Ramirez, B. Alemayehu, J. Lowrie, S. F. Hicks, J. R. Vanhoy, M. T. McEllistrem, S. Mukhopadhyay, E. E. Peters, S. W. Yates

AIP Conf. Proc. 2160, 050022 (2019)

https://doi.org/10.1063/1.5127714

Published: October 2019

View article titled, Undergraduate education at the University of Kentucky accelerator laboratory

Journal Articles

Measurements of activation cross section for ¹⁹⁸Pt(n,2n)^197mPt reaction induced by 14.7 MeV neutrons

N. Belouadah, F. Kadem, M. Belgaid, Z. Idiri, F. Redjem

AIP Conf. Proc. 1994, 020002 (2018)

https://doi.org/10.1063/1.5048138

Published: August 2018

View article titled, Measurements of activation cross section for 198Pt(n,2n)197mPt reaction induced by 14.7 MeV neutrons

Journal Articles

Thermo-luminescence and neutron absorption cross section evaluations of compounds of Lithium based oxide ceramic breeders in Li-Zr-O system

Sumanta Mukherjee, Yeshwant Naik

AIP Conf. Proc. 1942, 140003 (2018)

https://doi.org/10.1063/1.5029134

Published: April 2018

View article titled, Thermo-luminescence and neutron absorption cross section evaluations of compounds of Lithium based oxide ceramic breeders in Li-Zr-O system

Journal Articles

Theoretical calculations of double differential neutron emission cross sections of ²⁰⁹Bi at 14.2 MeV incident neutron energy

Muhittin Sahan, Eyyup Tel, Halide Sahan, Ismail Hakki Sarpun

AIP Conf. Proc. 1935, 100001 (2018)

https://doi.org/10.1063/1.5025989

Published: February 2018

View article titled, Theoretical calculations of double differential neutron emission cross sections of 209Bi at 14.2 MeV incident neutron energy

Journal Articles

Development of neutron shielding concrete containing iron content materials

Demet Sariyer, Rahmi Küçer

AIP Conf. Proc. 1935, 100003 (2018)

https://doi.org/10.1063/1.5025991

Published: February 2018

View article titled, Development of neutron shielding concrete containing iron content materials

Journal Articles

Applying an analytical method to study neutron behavior for dosimetry

S. A. Mousavi Shirazi

AIP Conf. Proc. 1790, 150004 (2016)

https://doi.org/10.1063/1.4968743

Published: December 2016

View article titled, Applying an analytical method to study neutron behavior for dosimetry

Journal Articles

2n-emission from ²⁰⁵Pb* nucleus using clusterization approach at E_beam∼14-20 MeV

Amandeep Kaur, Kiran Sandhu, Manoj Kumar Sharma

AIP Conf. Proc. 1728, 020424 (2016)

https://doi.org/10.1063/1.4946475

Published: May 2016

View article titled, 2n-emission from 205Pb* nucleus using clusterization approach at Ebeam∼14-20 MeV

Journal Articles

The perturbation of backscattered fast neutrons spectrum caused by the resonances of C, N and O for possible use in pyromaterial detection

Ahmad Firdaus Zainal Abedin, Noorddin Ibrahim, Noriza Ahmad Zabidi, Abqari Luthfi Albert Abdullah

AIP Conf. Proc. 1659, 030005 (2015)

https://doi.org/10.1063/1.4916853

Published: April 2015

View article titled, The perturbation of backscattered fast neutrons spectrum caused by the resonances of C, N and O for possible use in pyromaterial detection

Journal Articles

A Bayesian method to estimate the neutron response matrix of a single crystal CVD diamond detector

Marcel Reginatto, Francis Gagnon-Moisan, Jorge Guerrero Araque, Ralf Nolte, Miroslav Zbořil, Andreas Zimbal

AIP Conf. Proc. 1641, 321–328 (2015)

https://doi.org/10.1063/1.4905994

Published: January 2015

View article titled, A Bayesian method to estimate the neutron response matrix of a single crystal CVD diamond detector

Journal Articles

Measurements of neutron capture cross section for 207,208 Pb

M. Segawa, Y. Toh, H. Harada, F. Kitatani, M. Koizumi, T. Fukahori, M. Oshima, N. Iwamoto, O. Iwamoto, Y. Hatsukawa, Y. Nagai, M. Igashira, S. Kamada, M. Tajika

AIP Conf. Proc. 1594, 339–344 (2014)

https://doi.org/10.1063/1.4874092

Published: May 2014

View article titled, Measurements of neutron capture cross section for 207,208 Pb

Journal Articles

Neutron spectrometry using LNL bonner spheres and FLUKA

L. Sarchiapone, D. Zafiropoulos

AIP Conf. Proc. 1530, 163–170 (2013)

https://doi.org/10.1063/1.4812919

Published: July 2013

View article titled, Neutron spectrometry using LNL bonner spheres and FLUKA

NARROW

Topics

Calculation of neutron flux distribution and diffusion coefficient in the slab reactor core using multi-group diffusion equation with Jacobi method

Model calculation and evaluation of neutron induced reaction cross-section on 237_Np, 241_Am and 245_Cm using EMPIRE 3.2 code

Sample-induced perturbations in neutron field

Estimation of KERMA because of neutron emission into the constituent elements of a tissue in radiotherapy

Neutron flux distribution of slab reactor core using one-dimensional multi-group diffusion equation in the thermal energy region

Feasibility study of axial compact neutron generator as SAMOP neutron source

A new investigation into the estimation of transferred energy from a neutron source to a human’s body

Theoretical calculations involving a standard neutron yield distribution for the T-T nuclear fusion reaction

Effect of boron impurity and graphite thermal neutron scattering on criticality calculation of Indonesian experimental power reactor

Undergraduate education at the University of Kentucky accelerator laboratory

Measurements of activation cross section for ¹⁹⁸Pt(n,2n)^197mPt reaction induced by 14.7 MeV neutrons

Thermo-luminescence and neutron absorption cross section evaluations of compounds of Lithium based oxide ceramic breeders in Li-Zr-O system

Theoretical calculations of double differential neutron emission cross sections of ²⁰⁹Bi at 14.2 MeV incident neutron energy

Development of neutron shielding concrete containing iron content materials

Applying an analytical method to study neutron behavior for dosimetry

2n-emission from ²⁰⁵Pb* nucleus using clusterization approach at E_beam∼14-20 MeV

The perturbation of backscattered fast neutrons spectrum caused by the resonances of C, N and O for possible use in pyromaterial detection

A Bayesian method to estimate the neutron response matrix of a single crystal CVD diamond detector

Measurements of neutron capture cross section for 207,208 Pb

Neutron spectrometry using LNL bonner spheres and FLUKA

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