Safety analysis of spent fuel storage facility for BAEC TRIGA research reactor using MCNP5

被引：0

作者：

Soner, Md Abdul Malek ^{[1
]}

Hasan, Md Rakibul ^{[1
]}

Al Mahmud, Abdullah ^{[1
]}

Jahan, Nusrat ^{[1
]}

Uddin, Mohammad Mezbah ^{[1
]}

Haque, Ashraful ^{[1
]}

Rabir, Mohamad Hairie ^{[2
]}

机构：

[1] Centre for Research Reactor (CRR), Atomic Energy Research Establishment, Bangladesh Atomic Energy Commission (BAEC), Ganakbari, Dhaka, Savar, Bangladesh

[2] Nuclear and Reactor Physics Section, Reactor Technology Division, Malaysian Nuclear Agency, Selangor, Bangi, Malaysia

来源：

International Journal of Nuclear Energy Science and Technology | 2024年 / 17卷 / 2-3期

关键词：

Gas fuel storage - Radioactive waste disposal - Radioactive waste storage - Reactor refueling - Reactor shielding - Research reactors;

D O I：

10.1504/IJNEST.2024.142744

中图分类号：

学科分类号：

摘要：

Storage of the spent nuclear fuel of research reactors is always a challenge as storage could be needed for more than 50 years until a decision is made about the disposal. This paper describes the research work to analyse safety features of the wet type spent fuel storage facility for BAEC TRIGA Research Reactor (BTRR). MCNP5 code was used to design 7×7 array for BTRR fuel storage. The fuel pitch distance was found to be 10 cm (centre to centre) to maintain subcritical condition and Keff 0.645 (less than recommended value 0.8). The modelled design was able to withstand full load capacity of fuel. The large shielding margin space of the water height between 2.5 to 5 metre can be used for experiment, testing and upside fuel movements from racks. From the results, the designed spent fuel storage facility seems suitable for storing spent fuels. © 2024 Inderscience Enterprises Ltd.

引用

页码：99 / 115

共 50 条

[21] Criticality safety assessment of a TRIGA reactor spent-fuel pool under accident conditions
Glumac, B
Ravnik, M
Logar, M
NUCLEAR TECHNOLOGY, 1997, 117 (02) : 248 - 254
[22] Radiation streaming analysis in the radial and tangential ream tubes of a TRIGA research reactor using MCNP and comparison with measurement
Lee, JB
Lee, BW
Lee, BC
NUCLEAR SCIENCE AND ENGINEERING, 1995, 121 (02) : 334 - 344
[23] Safety for transportation, reloading, and storage of VVER-1000 reactor spent fuel at the RT-2 plant storage facility
Tsidvintsev, VV
NUCLEAR MATERIALS SAFETY MANAGEMENT, 1998, 20 : 143 - 154
[24] Preparation for shipment of spent TRIGA fuel elements from the research reactor of the Medical University of Hannover
Hampel, G
Cordes, H
Ebbinghaus, K
Haferkamp, D
RRFM'98: 2ND INTERNATIONAL TOPICAL MEETING ON RESEARCH REACTOR FUEL MANAGEMENT: INVITED AND CONTRIBUTED PAPERS - ORAL AND POSTER PRESENTATIONS, 1998, : 136 - 140
[25] Fuel burnup analysis and fuel management for TRIGA Mark III research reactor
Tiyapun, K.
Tippayakul, C.
Wetchagarun, S.
INTERNATIONAL NUCLEAR SCIENCE AND TECHNOLOGY CONFERENCE, 2019, 1285
[26] Extensions of the MCNP5 and TRIPOLI4 Monte Carlo Codes for Transient Reactor Analysis
Hoogenboom, J. Eduard
Sjenitzer, Bart L.
SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, 2014,
[27] Analysis for seismic response of dry storage facility for spent fuel
Ko, Yung-Yen
Hsu, Shang-Yi
Chen, Cheng-Hsing
NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (01) : 158 - 168
[28] Skyshine analysis of a spent fuel Dry Storage Facility with MCBEND
de Wouters, R
Quoidbach, A
PROCEEDINGS OF THE 1996 TOPICAL MEETING RADIATION PROTECTION & SHIELDING, VOLS 1 AND 2, 1996, 1-2 : 828 - 834
[29] Computational burnup analysis of the TRIGA Mark II research reactor fuel
Pungercic, Anze
Calic, Dusan
Snoj, Luka
PROGRESS IN NUCLEAR ENERGY, 2020, 130
[30] Estimation of the Dose Rate of Spent Fuel-Related Components of Lingao Nuclear Power Plant Using ORIGEN2 and MCNP5
XIE Mingliang
XIE Fei
SHAN Fuchang
XIE Zhengquan
LI Mingrui
SHI Hao
Wuhan University Journal of Natural Sciences, 2019, 24 (01) : 64 - 70

← 1 2 3 4 5 →