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    <title>NISCAIR Online Periodicals Repository Collection: IJPAP Vol.50(07) [July 2012]</title>
    <link>http://nopr.niscair.res.in/handle/123456789/14284</link>
    <description />
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        <rdf:li resource="http://nopr.niscair.res.in/handle/123456789/14322" />
        <rdf:li resource="http://nopr.niscair.res.in/handle/123456789/14321" />
        <rdf:li resource="http://nopr.niscair.res.in/handle/123456789/14320" />
        <rdf:li resource="http://nopr.niscair.res.in/handle/123456789/14319" />
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    <title>The Collection's search engine</title>
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  <item rdf:about="http://nopr.niscair.res.in/handle/123456789/14322">
    <title>Device for mechanoluminescence excitation by applying gradually varying pressure on the sample</title>
    <link>http://nopr.niscair.res.in/handle/123456789/14322</link>
    <description>Title: Device for mechanoluminescence excitation by applying gradually varying pressure on the sample
&lt;br/&gt;
&lt;br/&gt;Authors: Rai, R K; Kher, R S; S A, Khan; Dhoble, S J; Upadhyay, A K
&lt;br/&gt;
&lt;br/&gt;Abstract: A low cost set-up&#xD;
has been designed and developed for producing mechanoluminescence (ML) by&#xD;
continuously varying pressure on the sample. The ML of γ-irradiated BaAl&lt;sub&gt;2&lt;/sub&gt;O&lt;sub&gt;4&lt;/sub&gt;:Eu&#xD;
phosphor has been studied. ML is excited impulsively by dropping a load through&#xD;
guiding cylinder and by applying continuously varying pressure on the sample.&#xD;
When BaAl&lt;sub&gt;2&lt;/sub&gt;O&lt;sub&gt;4&lt;/sub&gt;:Eu phosphor is deformed impulsively, a&#xD;
single peak with shoulder is observed in the time versus ML intensity curve,&#xD;
while number of peak is observed when continuously increasing pressure applied&#xD;
on to the sample. When pressure is continuously decreased less number of peaks&#xD;
is observed as compared to that of increasing pressure. The enhancement in ML&#xD;
intensity with &lt;span style="mso-bidi-font-weight:bold"&gt;γ-irradiation suggests&#xD;
that BaAl&lt;sub&gt;2&lt;/sub&gt;O&lt;sub&gt;4&lt;/sub&gt;:Eu is a suitable candidate for ML dosimetry.&#xD;
&#xD;
&lt;/span&gt;
&lt;br/&gt;
&lt;br/&gt;Page(s): 534-537</description>
  </item>
  <item rdf:about="http://nopr.niscair.res.in/handle/123456789/14321">
    <title>Angular distribution of the ambient neutron dose equivalent from incidence of alpha particles on thick Al target</title>
    <link>http://nopr.niscair.res.in/handle/123456789/14321</link>
    <description>Title: Angular distribution of the ambient neutron dose equivalent from incidence of alpha particles on thick Al target
&lt;br/&gt;
&lt;br/&gt;Authors: Shanbhag, A A; Tripathy, S P; Sahoo, G S; Sunil, C; Nandy, M; Sarkar, P K
&lt;br/&gt;
&lt;br/&gt;Abstract: &lt;span style="font-size:10.0pt;font-family:&#xD;
" times="" new="" roman";mso-fareast-font-family:"times="" roman";mso-bidi-font-family:="" mangal;mso-ansi-language:en-us;mso-fareast-language:en-us;mso-bidi-language:="" hi"="" lang="EN-US"&gt;In this study, the measured data of angular distribution of neutron dose&#xD;
equivalent due to neutrons arising from the bombardment of 19.8 and 30 MeV&#xD;
alpha particles on a thick aluminium target has been reported. These&#xD;
measurements have been carried out at the BARC-TIFR Pelletron Linac Accelerator&#xD;
Facility using neutron dose equivalent meters popularly known as REM meters.&#xD;
The neutron dose equivalent values measured at a distance of 1 m from the&#xD;
target at various angles relative to the incident beam direction are presented&#xD;
here. The values are compared with those predicted by the empirical formulation&#xD;
of Clapier &amp;amp; Zaidins.&lt;/span&gt;
&lt;br/&gt;
&lt;br/&gt;Page(s): 531-533</description>
  </item>
  <item rdf:about="http://nopr.niscair.res.in/handle/123456789/14320">
    <title>Shield design for a hull neutron monitor using Monte Carlo techniques</title>
    <link>http://nopr.niscair.res.in/handle/123456789/14320</link>
    <description>Title: Shield design for a hull neutron monitor using Monte Carlo techniques
&lt;br/&gt;
&lt;br/&gt;Authors: Anand, S; Singh, Kapil Deo; Sharma, V K
&lt;br/&gt;
&lt;br/&gt;Abstract: &lt;span style="font-size:10.0pt;font-family:&#xD;
" times="" new="" roman";mso-fareast-font-family:"times="" roman";mso-bidi-font-family:="" mangal;mso-ansi-language:en-us;mso-fareast-language:en-us;mso-bidi-language:="" hi"="" lang="EN-US"&gt;In the head-end process of a reprocessing plant, the spent fuel is chopped&#xD;
using a mechanical chopper into small pieces and the heavy metal oxide is&#xD;
leached in nitric acid leaving behind the undissolved zircaloy clad (hull) in&#xD;
the basket. The hull mass needs to be estimated for the residual actinides and&#xD;
fission products to check for the completion of dissolution and also for the&#xD;
purpose of nuclear material accounting. This is normally carried out by gamma&#xD;
spectroscopy for the residual fission products. A new method is proposed based&#xD;
on active/passive neutron measurements of the residual actinides. The basket&#xD;
along with the hull is moved to a corner of the dissolution cell using remote tools,&#xD;
where the hull monitoring exercise will be carried out. Hence, shielding around&#xD;
this basket is required in this area to limit the dose rate to a value&#xD;
acceptable (i) for the operating personnel engaged in monitoring, and (ii) for &lt;sup&gt;3&lt;/sup&gt;He&#xD;
detectors used to measure neutrons. It has been proposed that the acceptable&#xD;
dose rate criteria at this detector location should be less than 1.74 mGy/hr&#xD;
(200 mR/hr). ORIGEN2 code is used to calculate the gamma and neutron emission&#xD;
rate from the residual spent fuel and the clad material in the hulls. Shielding&#xD;
code based on Monte Carlo technique is used&#xD;
for the gamma and neutron shielding calculations. In this paper, calculations&#xD;
are carried out for each of the shield material considered, and it is found&#xD;
that the shielding thickness required to bring down the dose rate to 1.74&#xD;
mGy/hr is 12.5 cm for lead or 21 cm for iron. &lt;/span&gt;
&lt;br/&gt;
&lt;br/&gt;Page(s): 527-530</description>
  </item>
  <item rdf:about="http://nopr.niscair.res.in/handle/123456789/14319">
    <title>Comparison of methodologies of gamma ray spectrometer and X-ray fluorescence</title>
    <link>http://nopr.niscair.res.in/handle/123456789/14319</link>
    <description>Title: Comparison of methodologies of gamma ray spectrometer and X-ray fluorescence
&lt;br/&gt;
&lt;br/&gt;Authors: Cunha, P D; Narayana, Y
&lt;br/&gt;
&lt;br/&gt;Abstract: Gamma-ray&#xD;
spectrometric analysis is often considered as an ideal method for thorium&#xD;
analysis, which would otherwise require the use of more tedious, time consuming&#xD;
and often less precise chemical methods. With the development of rare earth&#xD;
research, X-ray fluorescence spectrometry analysis has become an important&#xD;
means of rare earth elements analysis and has been playing an increasingly&#xD;
important role. In the present study, the XRF-spectrometry and&#xD;
gamma-spectrometric techniques have been carried out in determining the&#xD;
concentration of thorium in monazite bearing sand samples. Monazite is the&#xD;
principal source of thorium and the rare earth elements but its composition and&#xD;
the distribution may vary within very wide limits. Both XRF and Gamma-ray&#xD;
spectrometry techniques use uncharged radiation, although of different in&#xD;
origin, to identify and estimate concentrations of elements present in the&#xD;
sample. However, the XRF method is much quicker and the amount of sample needed&#xD;
for analysis is much less compared to gamma spectrometry analysis. The correlation study of the results obtained by&#xD;
these two methods was analysed and compared.
&lt;br/&gt;
&lt;br/&gt;Page(s): 524-526</description>
  </item>
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