Three dimensional analysis of temperature effect on control rod worth in TRR |
Yari, Maedeh
(Department of Physics, K.N. Toosi University of Technology)
Lashkari, Ahmad (Reactors and Accelerators Research and Development School, Nuclear Science and Technology, Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI)) Masoudi, S. Farhad (Department of Physics, K.N. Toosi University of Technology) Hosseinipanah, Mirshahram (Reactors and Accelerators Research and Development School, Nuclear Science and Technology, Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI)) |
1 | J.R. Lamarsh, A.J. Baratta, Introduction to Nuclear Engineering, 2001. |
2 | J.J. Duderstadt, L.J. Hamilton, Nuclear Reactor Analysis, Wiley & Sons, Inc., New York, 1976. |
3 | D.L. Hetrick, Dynamics of Nuclear Reactors, 1971. |
4 | P. Savva, M. Varvayanni, N. Catsaros, Dependence of control rod worth on fuel burnup, Nucl. Eng. Des. 241 (2) (2011) 492-497. DOI |
5 | E. Boafo, et al., Assessing the effect of fuel burnup on control rod worth for HEU and LEU cores of gharr-1, Res. J. Appl. Sci. Eng. Technol. 5 (4) (2013) 1129-1133. DOI |
6 | AEOI, Safety Analysis Report for the Tehran Research Reactor, LEU), Tehran-Iran, 2009. |
7 | INVAP, POS-WIMS V2.0. Program to Condense and Homogenize Macroscopic Cross-section WIMS Output. MTR-pc Package, Nuclear Engineering Division, INVAP, Bariloche, 2006d. |
8 | INVAP, MTR-pc V. 3.0. Neutronic, Thermal Hydraulic and Shielding Calculations on Personal Computers, Nuclear Engineering Division, INVAP, Bariloche., 2006e. |
9 | T. Kulikowska, WIMSD-5B: a Neutronic Code for Standard Lattice Physics Analysis, Distributed by NEA Data Bank, Saclay, France, 1996. |
10 | ORNL, WIMS-D4: Winfrith Improved Multigroup Scheme Code System. Code CCC-575, Oak Ridge National Laboratory, Oak Ridge, TN, 1991. |
11 | INVAP, HXS V. 4.1, MTR-pc Package, Macroscopic Cross Section Library Manager. Nuclear Engineering Division, INVAP, Bariloche., 2006c. |
12 | INVAP, CITVAP V. 3.1 Reactor Calculation Code, Nuclear Engineering Division, INVAP, Bariloche, 2006b. |
13 | A. Lashkari, H. Khalafi, H. Kazeminejad, Effective delayed neutron fraction and prompt neutron lifetime of Tehran research reactor mixed-core, Ann. Nucl. Energy 55 (2013) 265-271. DOI |
14 | A. Lashkari, et al., Neutronic analysis for tehran research reactor mixed-core, Prog. Nucl. Energy 60 (2012) 31-37. DOI |
15 | CNSC, REACTOR PHYSICS, Science and Reactor Fundamentals - Reactor Physics, Technical Training Group, 2003. |
16 | X-5 Monte Carlo Team, MCNP-a General Monte Carlo N-particle Transport Code, Version 5, Los Alamose National Laboratory, Los Alamos, New Mexico, USA, 2003. |
17 | M.B. Chadwick, P. Oblozinsky, M. Herman, et al., ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, Nucl. Data Sheets 107 (2006) 2931-3060. DOI |