Passive Neutron Assay of Plutonium Materials: Monte Carlo Procedures to Simulate Generation of Neutron Pulse Trains and the Application of the Neutron Coincidence Counting Method-Reference-Cited by-同舟云学术

Passive Neutron Assay of Plutonium Materials: Monte Carlo Procedures to Simulate Generation of Neutron Pulse Trains and the Application of the Neutron Coincidence Counting Method

Published:1998-09 Issue:1 Volume:130 Page:141-152
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Dodaro A.¹,Frazzoli F. V.¹,Remetti R.¹

Affiliation:

1. University of Rome “La Sapienza,” Faculty of Engineering, “Energetica” Department Via A. Scarpa, 14, I 00161 Rome, Italy

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE98-A1996

Reference3 articles.

1. “MCNP—A General Purpose Monte Carlo Code for Neutron and Photon Transport,” LA-12625-M, J. F. BRIESMEISTER, Ed. Los Alamos National Laboratory (Nov. 1993).

2. D. REILLY, N. ENSSLIN, H. SMITH, Jr., and S. KREINER, “Passive Non Destructive Assay of Nuclear Materials,” NUREG-CR5550-LA-UR-90-732, Los Alamos National Laboratory.

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. DST-Neutron Detection;Journal of Advanced Physics;2016-03-01

2. Application of neutron well coincidence counting for plutonium determination in mixed oxide fuel fabrication plant;Journal of Radioanalytical and Nuclear Chemistry;2008-03-11

3. MCNP–REN: a Monte Carlo tool for neutron detector design;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2002-06