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1

Coupling CFAST fire modeling and SAPHIRE probabilistic assessment software for internal fire safety evaluation of a typical TRIGA research reactor

Saiedeh Safaei Arshi, Mohammadreza Nematollahi, Kamran Sepanloo

Journal:

Reliability Engineering & System Safety

Year:

2010

Language:

english

File:

PDF, 476 KB

english, 2010

2

Change points estimations of bathtub-shaped hazard functions

Aghazadeh Chakherloo, Robab, Pourgol-Mohammad, Mohammad, Sepanloo, Kamran

Journal:

International Journal of System Assurance Engineering and Management

Year:

2017

Language:

english

File:

PDF, 543 KB

english, 2017

3

Adsorptive separation of La(III) from aqueous solution via the synthesized [Zn(bim)2(bdc)] metal-organic framework

Allahyari, Sareh Ammari, Saberi, Reza, Sepanloo, Kamran, Lashkari, Ahmad

Journal:

Journal of Rare Earths

Year:

2020

File:

PDF, 1.05 MB

2020

4

Optimization of the core configuration design using a hybrid artificial intelligence algorithm for research reactors

Afshin Hedayat, Hadi Davilu, Ahmad Abdollahzadeh Barfrosh, Kamran Sepanloo

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 878 KB

english, 2009

5

Estimation of research reactor core parameters using cascade feed forward artificial neural networks

Afshin Hedayat, Hadi Davilu, Ahmad Abdollahzadeh Barfrosh, Kamran Sepanloo

Journal:

Progress in Nuclear Energy

Year:

2009

Language:

english

File:

PDF, 615 KB

english, 2009

6

Design Studies of a Multicusp Ion Source with FEMLAB Simulation

Fatemeh Khodadadi Azadboni, Mahmood Sedaghatizade, Kamran Sepanloo

Journal:

Journal of Fusion Energy

Year:

2010

Language:

english

File:

PDF, 673 KB

english, 2010

7

Optimization of designing the core fuel loading pattern in a VVER-1000 nuclear power reactor using the genetic algorithm

Rafiei Karahroudi, M., Mousavi Shirazi, S.A., Sepanloo, K.

Journal:

Annals of Nuclear Energy

Year:

2013

Language:

english

File:

PDF, 3.40 MB

english, 2013

8

Investigation of a LOCA in a typical MTR by a novel best-estimate code

Vadi, Roozbeh, Sepanloo, Kamran

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 7.20 MB

english, 2016

9

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance - Thermo-Hydraulic Calculation and Safety Analysis of the Tehran Research Reactor

Jafari, J., Firuzjaee, M. K., Khakshournia, S., Sepanloo, K., D’Auria, F.

Year:

2009

Language:

english

File:

PDF, 561 KB

english, 2009

10

Response of single cell with acute angle exposed to an external electric field

Sarbazvatan, Saber, Sardari, Dariush, Taheri, Nahid, Sepanloo, Kamran

Journal:

Medical Engineering & Physics

Year:

2015

Language:

english

File:

PDF, 650 KB

english, 2015

11

An improved porous media model for nuclear reactor analysis

Vadi, Roozbeh, Sepanloo, Kamran

Journal:

Nuclear Science and Techniques

Year:

2016

Language:

english

File:

PDF, 8.00 MB

english, 2016

12

A novel method for detecting and counting overlapping tracks in SSNTD by image processing techniques

Ab Azar, N., Babakhani, A., Broumandnia, A., Sepanloo, K.

Journal:

Radiation Measurements

Year:

2016

Language:

english

File:

PDF, 2.92 MB

english, 2016

13

A practical sensitivity analysis method for ranking sources of uncertainty in thermal–hydraulics applications

Pourgol-Mohammad, Mohammad, Hoseyni, Seyed Mohsen, Hoseyni, Seyed Mojtaba, Sepanloo, Kamran

Journal:

Nuclear Engineering and Design

Year:

2016

Language:

english

File:

PDF, 1.27 MB

english, 2016

14

Reassessment of the generic assumptions applied to the conventional analysis of the reactivity insertion accident in the MTRs using a novel coupled code

Vadi, Roozbeh, Sepanloo, Kamran

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 6.50 MB

english, 2016

15

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications - Assessment of Reliability of Emergency Core Cooling System (ECCS) of Bushehr Nuclear Power Plant

Sotoudeh, Mohammad, Sepanloo, Kamran

Year:

2009

Language:

english

File:

PDF, 256 KB

english, 2009

16

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications - A Hybrid Qualitative/Quantitative Uncertainty Importance Assessment Approach: Applications to Thermal-Hydraulics System Codes Calculations

Pourgol-Mohammad, Mohammad, Sepanloo, Kamran

Year:

2009

Language:

english

File:

PDF, 136 KB

english, 2009

17

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance - Survey on Methodologies for Thermal-Hydraulics System Codes Uncertainty Assessment

Pourgol-Mohammad, Mohammad, Sepanloo, Kamran

Year:

2009

Language:

english

File:

PDF, 983 KB

english, 2009

18

Elastic Stability Analysis of a Two-Layered Functionally Graded Cylindrical Shell under Axial Compression with the use of Energy Approach

Sepiani, H., Rastgoo, A., Ahmadi, M., Arani, A.Ghorbanpour, Sepanloo, K.

Journal:

Advanced Composites Letters

Year:

2009

File:

PDF, 2.81 MB

2009

19

Numerical Investigation of Regular and Hybrid Nanofluids Application as the Working Fluids on Thermal Performance of TPCT

Vadi, Roozbeh, Sepanloo, Kamran

Journal:

Journal of Thermal Science and Engineering Applications

Year:

2019

Language:

english

File:

PDF, 4.77 MB

english, 2019

20

An improved semi-implicit direct kinetics method for transient analysis of nuclear reactors

Vadi, Roozbeh, Sepanloo, Kamran

Journal:

Nuclear Science and Techniques

Year:

2019

File:

PDF, 2.53 MB

2019

21

THE VALIDATION OF COMPREHENSIVE SOFTWARE FOR THE ASSESSMENT OF RADIOLOGICAL IMPACTS ON HUMANS THROUGH BENCHMARK ANALYSIS WITH RADIOLOGICAL CODES

Shad, Ali Haghighi, Allaf, Mitra Athari, Masti, Darioush, Sepanloo, Kamran, Feghhi, Seyed Amir Hossein

Journal:

Radiation Protection Dosimetry

Year:

2020

File:

PDF, 1.68 MB

2020

22

Design and development of a comprehensive program for the assessment and analysis of environmental effects due to the release of radioactive materials from the stack of nuclear installations: A case study in Bushehr nuclear power plant

Delgarm, Navid, Sepanloo, Kamran, Shad, Ali Haghighi, Masti, Darioush

Journal:

Applied Radiation and Isotopes

Year:

2020

File:

PDF, 2.13 MB

2020

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