Search Results - 22137189500

Cryostat system for investigation on new neutron moderator materials at reactor TRIGA PUSPATI by Dris Z.B., Mohamed A.A.B., Hamid N.A., Azman A., Ahmad M.H.A.R.M., Jamro R., Yazid H.

Neutron scattering instrumentation at low power reactors for science, engineering and education by Farhi E., Mohamad Idris F., Mohamed A.A., Yazid H.B., Jamro R., Harun Al Rashid M., Mohamed Zin M.R.B.

Preliminary study to determine the maximum settling velocity and model parameter of Cu nanoparticle by settling method by Azman A., Yusoff M.Z., Hassan M.Z., Yazid H., Gunnasegaran P., Ng K.C.

Preliminary study of neutron absorption by concrete with boron carbide addition by Abdullah Y., Ariffin F.N.T., Hamid R., Yusof M.R., Zali N.M., Ahmad M.H.A.R.M., Yazid H., Ahmad S., Mohamed A.A.

Study of pipe thickness loss using a neutron radiography method by Mohamed A.A., Wahab A.A.B., Yazid H.B., Ahmad M.H.A.R.B.M., Jamro R.B., Azman A.B., Zin M.R.M., Idris F.M.

Composite material characterisation using an advanced small angle x-ray (SAXS) technique by Yazid H., Murshidi J.A., Jamro R., Megat Harun M.A., Mohamed A.A.

Other Authors: “…22137189500…”

Preliminary analysis of gamma and neutron irradiation on sand and activated carbon by using SEM, XRD and SAXS by Abu Bakar A.A., Pauzi A.M., Mohamed A.A., Idris F.M., Yazid H.

Proposal for grid computing for nuclear applications by Idris F.M., Abdullah W.A.T.W., Ibrahim Z.A., Zolkapli Z., Anuar A.A., Norjoharuddeen N., Ali M.A.B.M., Mohamed A.A., Ismail R., Ahmad A.R., Ismail S., Haris M.F.B., Sulaiman M.S.B., Aslan M.D.A.B., Samsudin N.B., Ibrahim M.B., Ahmad M.H.A.R.B.M., Yazid H.B., Jamro R.B., Azman A.B., Rahman A.B.A., Ibrahim M.R.B.M., Muhamad S.B.S., Hassan H., Sjaugi F.

Monte Carlo Simulation for Designing Collimator of the Neutron Radiography Facility in Malaysia by Jamro R., Kardjilov N., Hairierabir M., Zain M.R.M., Mohamed A.A., Ali N.M., Idris F., Ahmad M.H.A.R.M., Yazid K., Yazid H., Azman A., Mamat M.R.

Microstructural investigations of materials for low temperature co-fired ceramic (LTCC) based fuel cell using small angle neutron scattering by Mohamed A.A., Ahmad M.H., Ibrahim A., Azman A., Alias R., Ambak Z., Shapee S., Putra E.G., Patriati A., Sharom M.A., Yazid H., Mamat M.R., Karim J.A., Idris F.M., Yazid K., Zin M.R.

Design of sample carrier for neutron irradiation facility at TRIGA MARK II nuclear reactor by Abdullah Y., Hamid N.A., Mansor M.A., Ahmad M.H.A.R.M., Yusof M.R., Yazid H., Mohamed A.A.