Neutron energy spectra calculations in the low power research reactor
IR@NISCAIR: CSIR-NISCAIR, New Delhi - ONLINE PERIODICALS REPOSITORY (NOPR)
View Archive Info| Field | Value | |
| Creator |
Omar, H
Khattab, K Ghazi, N |
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| Date |
2011-10-27T06:20:55Z
2011-10-27T06:20:55Z 2011-11 |
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| Identifier |
0975-1041 (Online); 0019-5596 (Print)
http://hdl.handle.net/123456789/12948 |
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| Description |
723-730
The neutron energy spectra have been calculated in the fuel region, inner and outer irradiation sites of the zero power research reactor using the MCNP-4C code and the combination of the WIMS-D/4 transport code for generation of group constants and the three-dimensional CITATION diffusion code for core analysis calculations. The neutron energy spectrum has been divided into three regions and compared with the proposed empirical correlations. The calculated thermal and fast neutron fluxes in the low power research reactor MNSR inner and outer irradiation sites have been compared with the measured results. Better agreements have been noticed between the calculated and measured results using the MCNP code than those obtained by the CITATION code. |
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| Language |
en_US
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| Publisher |
NISCAIR-CSIR, India
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| Rights |
<img src='http://nopr.niscair.res.in/image/cc-license-sml.png'> <a href='http://creativecommons.org/licenses/by-nc-nd/2.5/in' target='_blank'>CC Attribution-Noncommercial-No Derivative Works 2.5 India</a>
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| Source |
IJPAP Vol.49(11) [November 2011]
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| Subject |
Neutron spectrum
WIMS-D/4 code CITATION code MCNP Miniature Neutron Source Reactor |
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| Title |
Neutron energy spectra calculations in the low power research reactor
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| Type |
Article
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