Abstract
This research is about feasibility study for using thorium-based fuel composition in commercial nuclear power reactors. The article describes comparison of different type of software resources for carrying out neutronic computations for reactor core. To carry out neutronphysical computations the following software resources were chosen: MCU-PTR, WIMSD-5B, WIMS-ANL. Results of research show that precision software MCU-PTR (Monte Carlo method) demonstrates most accuracy results of calculations. WIMS-family software can be used only for estimated calculations because of its one-dimensional geometrical model. However, isotopic concentrations in fuel assembles during fuel cycle are correct for all of three software. Moreover, showed software allow calculate changes of reactivity margin.
| Original language | English |
|---|---|
| Pages (from-to) | 428-431 |
| Number of pages | 4 |
| Journal | Journal of Industrial Pollution Control |
| Volume | 32 |
| Issue number | 2 |
| Publication status | Published - 2016 |
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Keywords
- Neutron-physical computations
- Neutronic code
- Nuclear fuel cycle
- Thermal-neutron reactors
- Thorium
ASJC Scopus subject areas
- Water Science and Technology
- Ocean Engineering
- Pollution
- Fluid Flow and Transfer Processes
- Atmospheric Science
Cite this
Use of thorium in thermal-neutron reactors : Computation model and comparison of neutronic codes. / Naymushin, A.; Chertkov, Y. U.; Lebedev, I.; Anikin, M.
In: Journal of Industrial Pollution Control, Vol. 32, No. 2, 2016, p. 428-431.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Use of thorium in thermal-neutron reactors
T2 - Computation model and comparison of neutronic codes
AU - Naymushin, A.
AU - Chertkov, Y. U.
AU - Lebedev, I.
AU - Anikin, M.
PY - 2016
Y1 - 2016
N2 - This research is about feasibility study for using thorium-based fuel composition in commercial nuclear power reactors. The article describes comparison of different type of software resources for carrying out neutronic computations for reactor core. To carry out neutronphysical computations the following software resources were chosen: MCU-PTR, WIMSD-5B, WIMS-ANL. Results of research show that precision software MCU-PTR (Monte Carlo method) demonstrates most accuracy results of calculations. WIMS-family software can be used only for estimated calculations because of its one-dimensional geometrical model. However, isotopic concentrations in fuel assembles during fuel cycle are correct for all of three software. Moreover, showed software allow calculate changes of reactivity margin.
AB - This research is about feasibility study for using thorium-based fuel composition in commercial nuclear power reactors. The article describes comparison of different type of software resources for carrying out neutronic computations for reactor core. To carry out neutronphysical computations the following software resources were chosen: MCU-PTR, WIMSD-5B, WIMS-ANL. Results of research show that precision software MCU-PTR (Monte Carlo method) demonstrates most accuracy results of calculations. WIMS-family software can be used only for estimated calculations because of its one-dimensional geometrical model. However, isotopic concentrations in fuel assembles during fuel cycle are correct for all of three software. Moreover, showed software allow calculate changes of reactivity margin.
KW - Neutron-physical computations
KW - Neutronic code
KW - Nuclear fuel cycle
KW - Thermal-neutron reactors
KW - Thorium
UR - http://www.scopus.com/inward/record.url?scp=85014069879&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85014069879&partnerID=8YFLogxK
M3 - Article
VL - 32
SP - 428
EP - 431
JO - Journal of Industrial Pollution Control
JF - Journal of Industrial Pollution Control
SN - 0970-2083
IS - 2
ER -