The impact of HEU to LEU conversion of commercial MNSR: Determination of neutron spectrum parameters in irradiation channels of NIRR-1 using MCNP code

► A computational method was used to assess the impact of conversion of MNS reactors on utilization. ► Neutron spectrum parameters in irradiation channels of NIRR-1 HEU and LEU cores were calculated. ► Data obtained for HEU core agree well with measured data, which underscores the computational meth...

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Published inAnnals of nuclear energy Vol. 39; no. 1; pp. 15 - 17
Main Authors Jonah, S.A., Ibrahim, Y.V., Ajuji, A.S., Onimisi, M.Y.
Format Journal Article
LanguageEnglish
Published Elsevier Ltd 2012
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Abstract ► A computational method was used to assess the impact of conversion of MNS reactors on utilization. ► Neutron spectrum parameters in irradiation channels of NIRR-1 HEU and LEU cores were calculated. ► Data obtained for HEU core agree well with measured data, which underscores the computational method. ► Results indicate that the impact of HEU to LEU conversion of commercial MNSR on utilization is minimal. Miniature Neutron Source Reactor (MNSR) facilities are equipped with 10 irradiation channels mainly for NAA and limited radioisotope production. A neutronics feasibility study has shown that it would be feasible to convert commercial MNSR from HEU (90.2%) to LEU (∼12.5%) fuel. In this work, the impact of the proposed LEU fuel on neutron spectrum parameters in the irradiation channels has been studied. The MCNP code was used to calculate the neutron flux distribution in 640 neutron energy group structure and the cross section data of monitor reactions also in 640 neutron energy group structure were extracted from ENDF libraries. On the basis of the data, the Cd ratios for Au, Co, Th, and U were computed and used to estimate the thermal-to-epithermal neutron ratio, f, as well as the non-ideality of epithermal neutron spectrum, α. In order to verify the calculations, measured experimental data for the current HEU core are compared with calculations. Results obtained indicate slightly “hardened” neutron spectra distributions in the inner and outer irradiation channels of the proposed LEU core with no significant impact on utilization.
AbstractList Miniature Neutron Source Reactor (MNSR) facilities are equipped with 10 irradiation channels mainly for NAA and limited radioisotope production. A neutronics feasibility study has shown that it would be feasible to convert commercial MNSR from HEU (90.2%) to LEU (a arrow right 412.5%) fuel. In this work, the impact of the proposed LEU fuel on neutron spectrum parameters in the irradiation channels has been studied. The MCNP code was used to calculate the neutron flux distribution in 640 neutron energy group structure and the cross section data of monitor reactions also in 640 neutron energy group structure were extracted from ENDF libraries. On the basis of the data, the Cd ratios for Au, Co, Th, and U were computed and used to estimate the thermal-to-epithermal neutron ratio, f, as well as the non-ideality of epithermal neutron spectrum, alpha . In order to verify the calculations, measured experimental data for the current HEU core are compared with calculations. Results obtained indicate slightly "hardened" neutron spectra distributions in the inner and outer irradiation channels of the proposed LEU core with no significant impact on utilization.
► A computational method was used to assess the impact of conversion of MNS reactors on utilization. ► Neutron spectrum parameters in irradiation channels of NIRR-1 HEU and LEU cores were calculated. ► Data obtained for HEU core agree well with measured data, which underscores the computational method. ► Results indicate that the impact of HEU to LEU conversion of commercial MNSR on utilization is minimal. Miniature Neutron Source Reactor (MNSR) facilities are equipped with 10 irradiation channels mainly for NAA and limited radioisotope production. A neutronics feasibility study has shown that it would be feasible to convert commercial MNSR from HEU (90.2%) to LEU (∼12.5%) fuel. In this work, the impact of the proposed LEU fuel on neutron spectrum parameters in the irradiation channels has been studied. The MCNP code was used to calculate the neutron flux distribution in 640 neutron energy group structure and the cross section data of monitor reactions also in 640 neutron energy group structure were extracted from ENDF libraries. On the basis of the data, the Cd ratios for Au, Co, Th, and U were computed and used to estimate the thermal-to-epithermal neutron ratio, f, as well as the non-ideality of epithermal neutron spectrum, α. In order to verify the calculations, measured experimental data for the current HEU core are compared with calculations. Results obtained indicate slightly “hardened” neutron spectra distributions in the inner and outer irradiation channels of the proposed LEU core with no significant impact on utilization.
Author Jonah, S.A.
Ajuji, A.S.
Ibrahim, Y.V.
Onimisi, M.Y.
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Cites_doi 10.1007/s10967-008-7347-8
10.1016/j.anucene.2009.05.001
10.1007/s10967-005-0873-8
10.1016/j.apradiso.2009.03.117
10.1016/j.anucene.2007.05.010
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References Jonah, Balogun, Umar, Mayaki (b0015) 2005; 266
Jonah, Liaw, Matos (b0020) 2007; 34
De Corte, F., 1987. The k
ENDF-Evaluated Nuclear Data File ENDF/B-VII.0 2006.
Briesmeister, J.F., 2000. MCNP-A General Monte Carlo N-Particle Transport Code Version 4C. LA-13709-M, Los Alamos National Laboratory, USA.
Standardization Method: A Move to the Optimization of Reactor Neutron Activation Analysis, Habil. Thesis, University of Gent.
Jonah, Ibikunle, Li (b0025) 2009; 36
Ke, Sun, Shen, Liu, Li, Zhou (b0035) 2009; 67
.
Jonah, Sadiq, Okunade, Funtua (b0030) 2009; 279
SAR, 2005. Final Safety Analysis Report of Nigeria Research Reactor-1. CERT Technical Report-CERT/NIRR-1/FSAR-01, CERT, ABU, Zaria, Nigeria.
Jonah (10.1016/j.anucene.2011.08.026_b0015) 2005; 266
Jonah (10.1016/j.anucene.2011.08.026_b0025) 2009; 36
Ke (10.1016/j.anucene.2011.08.026_b0035) 2009; 67
10.1016/j.anucene.2011.08.026_b0005
10.1016/j.anucene.2011.08.026_b0045
Jonah (10.1016/j.anucene.2011.08.026_b0020) 2007; 34
Jonah (10.1016/j.anucene.2011.08.026_b0030) 2009; 279
10.1016/j.anucene.2011.08.026_b0010
10.1016/j.anucene.2011.08.026_b0040
References_xml – volume: 266
  start-page: 83
  year: 2005
  end-page: 88
  ident: b0015
  article-title: Neutron spectrum parameters in irradiation channels of the Nigeria research reactor-1 (NIRR-1) for the k
  publication-title: J. Radioanal. Nucl. Chem.
  contributor:
    fullname: Mayaki
– volume: 279
  start-page: 749
  year: 2009
  end-page: 755
  ident: b0030
  article-title: The use of the k
  publication-title: J. Radioanal. Nucl. Chem.
  contributor:
    fullname: Funtua
– volume: 36
  start-page: 1285
  year: 2009
  end-page: 1286
  ident: b0025
  article-title: A feasibility study of LEU enrichment uranium fuels for MNSR conversion using MCNP
  publication-title: Ann. Nucl. Energy
  contributor:
    fullname: Li
– volume: 34
  start-page: 953
  year: 2007
  end-page: 957
  ident: b0020
  article-title: Monte Carlo simulation of core physics parameters of the Nigeria research reactor-1(NIRR-1)
  publication-title: Ann. Nucl. Energy
  contributor:
    fullname: Matos
– volume: 67
  start-page: 5234
  year: 2009
  end-page: 5237
  ident: b0035
  article-title: The study of physics and thermal characteristics for in-hospital neutron irradiator (INHI)
  publication-title: Appl. Radiat. Isot.
  contributor:
    fullname: Zhou
– ident: 10.1016/j.anucene.2011.08.026_b0045
– ident: 10.1016/j.anucene.2011.08.026_b0010
– volume: 279
  start-page: 749
  year: 2009
  ident: 10.1016/j.anucene.2011.08.026_b0030
  article-title: The use of the k0-IAEA program in NIRR-1 laboratory
  publication-title: J. Radioanal. Nucl. Chem.
  doi: 10.1007/s10967-008-7347-8
  contributor:
    fullname: Jonah
– volume: 36
  start-page: 1285
  year: 2009
  ident: 10.1016/j.anucene.2011.08.026_b0025
  article-title: A feasibility study of LEU enrichment uranium fuels for MNSR conversion using MCNP
  publication-title: Ann. Nucl. Energy
  doi: 10.1016/j.anucene.2009.05.001
  contributor:
    fullname: Jonah
– ident: 10.1016/j.anucene.2011.08.026_b0040
– ident: 10.1016/j.anucene.2011.08.026_b0005
– volume: 266
  start-page: 83
  year: 2005
  ident: 10.1016/j.anucene.2011.08.026_b0015
  article-title: Neutron spectrum parameters in irradiation channels of the Nigeria research reactor-1 (NIRR-1) for the k0-NAA standardization
  publication-title: J. Radioanal. Nucl. Chem.
  doi: 10.1007/s10967-005-0873-8
  contributor:
    fullname: Jonah
– volume: 67
  start-page: 5234
  year: 2009
  ident: 10.1016/j.anucene.2011.08.026_b0035
  article-title: The study of physics and thermal characteristics for in-hospital neutron irradiator (INHI)
  publication-title: Appl. Radiat. Isot.
  doi: 10.1016/j.apradiso.2009.03.117
  contributor:
    fullname: Ke
– volume: 34
  start-page: 953
  year: 2007
  ident: 10.1016/j.anucene.2011.08.026_b0020
  article-title: Monte Carlo simulation of core physics parameters of the Nigeria research reactor-1(NIRR-1)
  publication-title: Ann. Nucl. Energy
  doi: 10.1016/j.anucene.2007.05.010
  contributor:
    fullname: Jonah
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Miniature Neutron Source Reactor (MNSR) facilities are equipped with 10 irradiation channels mainly for NAA and limited radioisotope production. A neutronics...
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SubjectTerms Channels
Energy distribution
Energy use
Irradiation
LEU conversion
Mathematical analysis
MCNP
MNSR
Neutron spectrum parameters
NIRR-1
Nuclear power generation
Nuclear reactor components
Nuclear reactors
Title The impact of HEU to LEU conversion of commercial MNSR: Determination of neutron spectrum parameters in irradiation channels of NIRR-1 using MCNP code
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