Nuclear Fuel Cell Calculation Using Collision Probability Method with Linear Non Flat Flux Approach

Journals Menu

Follow SCIRP

ISSN Print: 2161-6795
ISSN Online: 2161-6809
www.scirp.org/journal/wjnst
E-mail: wjnst@scirp.org

Citations h5-index & Ranking

"Nuclear Fuel Cell Calculation Using Collision Probability Method with Linear Non Flat Flux Approach"
written by Mohamad Ali Shafii, Zaki Su’ud, Abdul Waris, Neny Kurniasih,
published by World Journal of Nuclear Science and Technology, Vol.2 No.2, 2012

has been cited by the following article(s):

[1]	Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction
	2021

[2]	Analisis Distribusi Fluks Neutron pada Reaktor Berbentuk Slab Menggunakan Persamaan Difusi Multigrup Satu Dimensi dengan Metode Gauss-Seidel
	2020

[3]	Analisis Koefisien Difusi Neutron terhadap Jarak Ekstrapolasi dalam Persamaan Difusi Multigrup Satu Dimensi
	2019

[4]	Neutron Distribution in the Nuclear Fuel Cell using Collision Probability Method with Quadratic Flux Approach
	IOP Conference Series: Materials Science and Engineering, 2017

[5]	PENGELOLAAN BAHAN BAKAR DAN LIMBAH NUKLIR: MENUJU ZERO RELEASE NUCLEAR WASTE
	2017

[6]	Perhitungan Matriks Pij dan Distribusi Fluks Neutron pada Sel Bahan Bakar Nuklir U-235 dan U-238 Berbentuk Slab Menggunakan MOC
	2017

[7]	Analysis of Neutron Fission Reaction Rate in the Nuclear Fuel Cell Using Collision Probability Method with Non Flat Flux Approach
	2017

[8]	Analisis Laju Reaksi Neutron Dalam Sel Bahan Bakar Nuklir Pada Reaktor Cepat
	2016

[9]	Self-Shielding Treatment to Perform Cell Calculation for Seed Furl In Th/U Pwr Using Dragon Code
	2015

[10]	POLA PENAMPANG LINTANG MAKROSKOPIK TOTAL DALAM SEL BAHAN BAKAR NUKLIR
	Jurnal Ilmu Fisika, 2014

[1]	Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction International Journal of Energy Research, 2021 DOI:10.1002/er.6384

[2]	Neutron Distribution in the Nuclear Fuel Cell using Collision Probability Method with Quadratic Flux Approach IOP Conference Series: Materials Science and Engineering, 2017 DOI:10.1088/1757-899X/180/1/012040

[3]	Analysis of Neutron Fission Reaction Rate in the Nuclear Fuel Cell Using Collision Probability Method with Non Flat Flux Approach Journal of Physics: Conference Series, 2017 DOI:10.1088/1742-6596/877/1/012013

[4]	POLA PENAMPANG LINTANG MAKROSKOPIK TOTAL DALAM SEL BAHAN BAKAR NUKLIR JURNAL ILMU FISIKA \| UNIVERSITAS ANDALAS, 2014 DOI:10.25077/jif.6.1.25-30.2014

Follow SCIRP