1993
DOI: 10.13182/nse92-94
|View full text |Cite
|
Sign up to set email alerts
|

Spent-Fuel Assay Performance and Monte Carlo Analysis of the Rensselaer Slowing-Down-Time Spectrometer

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1
1
1
1

Citation Types

0
7
0

Year Published

1997
1997
2017
2017

Publication Types

Select...
6
2

Relationship

0
8

Authors

Journals

citations
Cited by 15 publications
(7 citation statements)
references
References 5 publications
0
7
0
Order By: Relevance
“…A number of techniques have been explored for this objective including photofission to induce delayed neutron signatures [9], neutron-induced fission leading to coincident neutron signatures [10], and lead-slowing down spectroscopy [11]- [14].…”
Section: Introductionmentioning
confidence: 99%
“…A number of techniques have been explored for this objective including photofission to induce delayed neutron signatures [9], neutron-induced fission leading to coincident neutron signatures [10], and lead-slowing down spectroscopy [11]- [14].…”
Section: Introductionmentioning
confidence: 99%
“…Prior work in the application of LSDS to spent fuel demonstrated its potential for direct measurement of fissile isotopes 0018-9499/$26.00 © 2010 IEEE such as U-235, Pu-239, and Pu-241 in fuel assemblies, but also noted the severity of self-shielding and the resulting system nonlinearities [9]- [12]. The predicted statistical uncertainties for LSDS assay of fuel and a survey of degrading factors such as hydrogen buildup in the cladding and curium neutron background were explored in [13].…”
Section: Time-spectral Analysis Methods For Spent Fuel Assay Using Lementioning
confidence: 99%
“…The average flux over the homogenized parallelepiped volume, assuming a purely absorbing medium, is given by (8) from which an analytical self-shielding approximation can be deduced: (9) The linear attenuation coefficient in (9) is an effective attenuation coefficient calculated from the weighted mean of the constituent isotopes. This aggregate coefficient, therefore, can be expressed in terms of the microscopic cross sections for induced fission ( ) and absorption ( ) using the approximation that the effective density of attenuator is the unknown mass divided by the effective volume of the homogeneous fuel, ,…”
Section: (7)mentioning
confidence: 99%
“…The 12 NDA techniques being pursued are the following: Delayed Gamma [3], Delayed Neutrons [4], Differential Die-Away DDT [5], Lead Slowing Down Spectrometer LSDS [6], [7], Neutron Multiplicity [8], Nuclear Resonance Fluorescence NRF [9], Passive Prompt Gamma [10], Passive Neutron Albedo Reactivity PNAR [10], [11], [12], Selfintegration Neutron Resonance Densitometry SINRD [13], [14] Total Neutron (Gross Neutron) [2], X-Ray Fluorescence [15], 252 Cf Interrogation with Prompt Neutron Detection. These techniques vary greatly in maturity and the amount of previous research work carried out.…”
Section: Methodsmentioning
confidence: 99%