Calculations of fuel burn-up and radionuclide inventory in the syrian miniature neutron source reactor using the WIMSD4 code

被引：11

作者：

Khattab, K ^{[1
]}

机构：

[1] Atom Energy Commiss, Dept Nucl Engn, Damascus, Syria

来源：

ANNALS OF NUCLEAR ENERGY | 2005年 / 32卷 / 10期

关键词：

D O I：

10.1016/j.anucene.2005.02.011

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Calculations of the fuel burn up and radionuclide inventory in the Miniature Neutron Source Reactor after 10 years (the reactor core expected life) of the reactor operating time are presented in this paper. The WIMSD4 code is used to generate the fuel group constants and the infinite multiplication factor versus the reactor operating time for 10, 20, and 30 kW operating power levels. The amounts of uranium burnt up and plutonium produced in the reactor core, the concentrations and radioactivities of the most important fission product and actinide radionuclides accumulated in the reactor core, and the total radioactivity of the reactor core are calculated using the WIMSD4 code as well. (c) 2005 Elsevier Ltd. All rights reserved.

引用

页码：1122 / 1130

页数：9

共 24 条

[1] Calculation of fuel burnup and radionuclide inventory in the Syrian miniature neutron source reactor using the GETERA code
Khattab, K.
Dawahra, S.
ANNALS OF NUCLEAR ENERGY, 2011, 38 (06) : 1442 - 1446
[2] Four energy group neutron flux distributions in the Syrian Miniature Neutron Source Reactor using the WIMSD4 and CITATION codes
Khattab, K.
Omar, H.
Ghazi, N.
PROGRESS IN NUCLEAR ENERGY, 2009, 51 (02) : 297 - 302
[3] Calculations of the thermal and fast neutron fluxes in the Syrian miniature neutron source reactor using the MCNP-4C code
Khattab, K.
Sulieman, I.
APPLIED RADIATION AND ISOTOPES, 2009, 67 (04) : 535 - 538
[4] Time dependent burn-up and fission products inventory calculations in the discharged fuel of the Syrian MNSR
Omar, H.
Ghazi, N.
ANNALS OF NUCLEAR ENERGY, 2011, 38 (08) : 1698 - 1704
[5] Miniature neutron source reactor burnup calculations using IRBURN code system
Feghhi, S. A. H.
Jafarikia, S.
Abtin, F.
ANNALS OF NUCLEAR ENERGY, 2012, 47 : 242 - 248
[6] Calculation of fuel burn up and radioactive inventory in a CANDU reactor using WIMS-D4 code
Yasin, Zafar
ANNALS OF NUCLEAR ENERGY, 2010, 37 (01) : 66 - 70
[7] Analysis of Fuel Burn-up Calculations of 3600 MWth Sodium-cooled Fast Reactor Core
Ibrahim, Amr
ARAB JOURNAL OF NUCLEAR SCIENCES AND APPLICATIONS, 2021, 54 (03): : 112 - 118
[8] Investigation on Neutron Flux Effect onto Irradiated Fuel Burn-up Stored in the Reactor TRIGA PUSPATI
Husain, M. A. A.
Hashim, S.
Bradley, D.
Rabir, M. H.
Zakaria, N.
Zin, M. R. M.
ATOM INDONESIA, 2019, 45 (01) : 59 - 65
[9] Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code
Gholamzadeh, Zohreh
Feghhi, Seyed Amir Hossein
Soltani, Leila
Rezazadeh, Marzieh
Tenreiro, Claudio
Joharifard, Mandi
NUKLEONIKA, 2014, 59 (04) : 129 - 136
[10] Evaluation of Fuel Burn-up and Radioactivity Inventory in the 2 MW TRIGA-Plate Bandung Research Reactor
Setiawan, M. Budi
Kuntjoro, S.
Udiyani, P. M.
Husnayani, I.
SYMPOSIUM OF EMERGING NUCLEAR TECHNOLOGY AND ENGINEERING NOVELTY (SENTEN 2018), 2019, 1198

← 1 2 3 →