Development of Gadolinium (neutron poison) monitoring system for fuel reprocessing facilities: Computational model and validation with experiments

Author:

Chandrasekaran S.ORCID,Basu Pew,Krishnan H.,Sivasubramanian K.,Baskaran R.,Venkatraman B.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference5 articles.

1. MCNP – a General Monte Carlo N -Particle Transport Code – Version 4C,2000

2. A non-intrusive neutron method for poison concentration monitoring in CANDU reactors;Hussein;Nucl. J. Can.,1987

3. A comparative study of dose transmission factor of polythene and borated polythene for high neutron source shielding;Igwesi;Int. J. Sci. Technol. Res.,2013

4. Neutron capture and total cross-section measurements and resonance parameters of Gadolinium;Leinweber;Nucl. Sci. Eng.,2006

5. Criticality of Plutonium nitrate Solution containing soluble Gadolinium;Lloyd;Nucl. Sci. Eng.,1972

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