Neutron spectrum parameters in irradiation channels of the Nigeria Research Reactor-1 (NIRR-1) for the k0-NAA standardization

Jonah, S.A.; Balogun, G.I.; Ibrahim, Umar; Mayaki, MC

doi:10.1007/s10967-005-0873-8

Cited by 33 publications

(10 citation statements)

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“…From the results, absolute thermal, epithermal and fast neutron flux data in an inner irradiation channel B2 are comparable with our previous results [9,10]. In the Cdlined outer irradiation channel, the absolute value of the fast neutron flux is slightly three times greater than the epithermal flux.…”

Section: From the Data Insupporting

confidence: 89%

“…The induced radioactivities based on 64 Cu, 27 Mg and 198 Au residual radionuclides were measured on a well calibrated gamma ray spectrometry set up consist of a HPGe detector and electronic modules. Detail description of our gamma ray spectrometry set up has been described elsewhere [9,10]. The description of the monitor foils and nuclear data of nuclear reactions used in this work are presented in Table 1.…”

Section: Methodsmentioning

confidence: 99%

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An Investigation of the Impact of Installation of Cd-Lined Irradiation Channel in NIRR-1 on Core Physics Data for ENAA

Jonah¹,

Njinga²,

Ibrahim³

2014

WJNST

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Prior to the installation of the Cd-liner in one of the large outer irradiation channels of NIRR-1, a Monte Carlo simulation was performed using MCNP5 version 1.4 code. This was done to investigate the effect of installation of Cd-liner in either an inner or outer irradiation channel on reactor physics parameters. Data obtained indicate that the core excess reactivity in both inner and outer irradiations channels is reduced by 3.60 ± 0.07 mk and 0.64 ± 0.06 mk, respectively. Considering the fact that NIRR-1 has a cold core excess reactivity of 3.77 mk, results obtained show that installation of the 1 mm thick Cd-sheet in one of the large outer irradiation channels would have no significant impact on the core physics data. After installation of a 1 mm Cd sheath in a large outer irradiation channel, the neutron flux distribution and the stability in the irradiation channels were monitored by foil activation method. Results indicate that the uniformity of neutron flux distribution in the irradiation channel is preserved and the neutron flux data were found to be comparable with the data obtained before the installation.

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Section: From the Data Insupporting

confidence: 89%

Section: Methodsmentioning

confidence: 99%

An Investigation of the Impact of Installation of Cd-Lined Irradiation Channel in NIRR-1 on Core Physics Data for ENAA

Jonah¹,

Njinga²,

Ibrahim³

2014

WJNST

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“…In general, the neutron spectrum parameters α obtained in this work for the irradiation channels of GHARR-1 being considered compares very well with the α values obtained by Akaho et al on the same reactor in 2002 [18].…”

Section: Neutron Shaping Factor (α) In the Irradiation Channelssupporting

confidence: 89%

Determination of Neutron Fluxes and Spectrum Shaping Factors in Irradiation Sites of Ghana’S Miniature Neutron Source Reactor (mnsr) by Activation Method After Compensation of Loss of Excess Reactivty

Sogbadji¹,

Nyarko²,

Akaho³

et al. 2011

WJNST

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Accurate neutron flux values in irradiation channels of research reactors are very essential to their usage. The total neutron flux of the Ghana Research Reactor-1 (GHARR-1) was measured after a beryllium reflector was added to its shim to compensate for excess reactivity loss. The thermal, epithermal and fast neutron fluxes were determined by the method of foil activation. The experimental samples with and without a cadmium cover of 1-mm thickness were irradiated in the isotropic neutron field of the irradiation sites of Ghana Research Reactor-1 facility. The induced activities in the sample were measured by gamma ray spectrometry with a high purity germanium detector. The necessary correction for gamma attenuation, thermal neutrons and resonance neutron self-shielding effects were taken into account during the experimental analysis. By defining cadmium cutoff energy of 0.55 eV, Al-0.1% Au wires of negligible thickness were irradiated at 3 kW to determine the neutron fluxes of two irradiation channels, outer channel 7 and inner channel 2 whose Neutron Shaping Factor (α) were found to be (0.037 ± 0.001) and (-0.961 ± 0.034). The neutron flux ratios at the inner irradiation site 2 were found to be, (25.308 ± 3.201) for thermal to epithermal neutrons flux, (0.179 ± 0.021) for epithermal to fast neutrons flux and (4.528 ± 0.524) for thermal to fast neutrons flux, in the outer irradiation site 7, the neutron flux ratios were found to be, (40.865 ± 3.622) for thermal to epithermal neutrons flux, (0.286 ± 0.025) for epithermal to fast neutrons flux and (11.680 ± 1.030) for thermal to fast neutrons flux.

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“…The k 0 -factor is independent of irradiation and measuring conditions thus, eliminating the problems of non-availability of standards for certain elements and the inaccuracy caused by poorly prepared in-house standards (Jonah et al, 2005). Our main objective is to determine activation cross section data in the framework of the IAEA Coordinated Research Project No.13728 entitled "Reference Database for NAA" using the NIRR-1 Facilities.…”

Section: Introductionmentioning

confidence: 99%

Determination of neutron-induced activation cross sections using nirr-1

Umar¹,

Jonah²,

Nasiru³

et al. 2010

Bayero J. Pure App. Sci.

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Neutron spectrum parameters in irradiation channels of the Nigeria Research Reactor-1 (NIRR-1) for the k0-NAA standardization

Cited by 33 publications

References 0 publications

An Investigation of the Impact of Installation of Cd-Lined Irradiation Channel in NIRR-1 on Core Physics Data for ENAA

An Investigation of the Impact of Installation of Cd-Lined Irradiation Channel in NIRR-1 on Core Physics Data for ENAA

Determination of Neutron Fluxes and Spectrum Shaping Factors in Irradiation Sites of Ghana’S Miniature Neutron Source Reactor (mnsr) by Activation Method After Compensation of Loss of Excess Reactivty

Determination of neutron-induced activation cross sections using nirr-1

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