MCNP6 simulations of gamma line emissions from fission products and their comparisons to plutonium and uranium measurements

Author:

Andrews M.T.,Goorley J.T.,Corcoran E.C.,Kelly D.G.

Funder

Advanced Simulations and Computing Program

NSERC

Publisher

Elsevier BV

Subject

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

Reference20 articles.

1. A system for the measurement of delayed neutrons and gammas from special nuclear materials;Andrews;Radioanal. Nucl. Chem.,2015

2. Modeling the detection of delayed neutron signatures in MCNP6 and comparison with 233U, 235U, and 239Pu measurements;Andrews;Nucl. Technol.,2014

3. Identification of fissile materials from fission product gamma-ray spectra;Beddingfield;Nucl. Instrum. Methods Phys. Res. A,1998

4. The application of mathematical modeling for commercial nuclear instrument design, development, and calibration;Bronson;Adv. Nucl. Instrum. Meas. Methods their Appl. IEEE 2009,2009

5. High-energy delayed gamma spectroscopy for spent nuclear fuel assay;Campbell;Nucl. Sci. IEEE Trans.,2011

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