Determining fissile content in PWR spent fuel assemblies using a passive neutron Albedo reactivity with fission chambers technique
Abstract
State regulatory bodies and organizations such as the IAEA that are concerned with preventing the proliferation of nuclear weapons are interested in a means of quantifying the amount of plutonium in a given spent fuel assembly. The complexity of spent nuclear fuel makes the measurement of plutonium content challenging. There are a variety of techniques that can measure various properties of spent nuclear fuel including burnup, and mass of fissile content. No single technique can provide all desired information, necessitating an approach using multiple detector systems and types. This paper presents our analysis of the Passive Neutron Albedo Reactivity Fission Chamber (PNAR-FC) detector system. PNAR-FC is a simplified version of the PNAR technique originally developed in 1997. This earlier research was performed with a high efficiency, {sup 3}He-based system (PNAR-3He) with which multiplicty analysis was performed. With the PNAR technique a portion of the spent fuel assembly is wrapped in a 1 mm thick cadmium liner. Neutron count rates are measured both with and without the cadmium liner present. The ratio of the count rate with the cadmium liner to the count rate without the cadmium liner is calculated and called the cadmium ratio. In the PNAR-3He technique, multiplicity measurementsmore »
- Authors:
-
- Los Alamos National Laboratory
- Publication Date:
- Research Org.:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1015240
- Report Number(s):
- LA-UR-10-03566; LA-UR-10-3566
TRN: US1102810
- DOE Contract Number:
- AC52-06NA25396
- Resource Type:
- Conference
- Resource Relation:
- Conference: Institute of Nuclear Materials Management 51st Annual Meeting ; July 11, 2010 ; Baltimore, MD
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION; ALBEDO; BURNUP; CADMIUM; EFFICIENCY; FISSION CHAMBERS; IAEA; LINERS; MULTIPLICITY; NEUTRONS; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; NUCLEAR WEAPONS; PLUTONIUM; PROLIFERATION; SPENT FUELS
Citation Formats
Conlin, Jeremy Lloyd, and Tobin, Stephen J. Determining fissile content in PWR spent fuel assemblies using a passive neutron Albedo reactivity with fission chambers technique. United States: N. p., 2010.
Web.
Conlin, Jeremy Lloyd, & Tobin, Stephen J. Determining fissile content in PWR spent fuel assemblies using a passive neutron Albedo reactivity with fission chambers technique. United States.
Conlin, Jeremy Lloyd, and Tobin, Stephen J. 2010.
"Determining fissile content in PWR spent fuel assemblies using a passive neutron Albedo reactivity with fission chambers technique". United States. https://www.osti.gov/servlets/purl/1015240.
@article{osti_1015240,
title = {Determining fissile content in PWR spent fuel assemblies using a passive neutron Albedo reactivity with fission chambers technique},
author = {Conlin, Jeremy Lloyd and Tobin, Stephen J},
abstractNote = {State regulatory bodies and organizations such as the IAEA that are concerned with preventing the proliferation of nuclear weapons are interested in a means of quantifying the amount of plutonium in a given spent fuel assembly. The complexity of spent nuclear fuel makes the measurement of plutonium content challenging. There are a variety of techniques that can measure various properties of spent nuclear fuel including burnup, and mass of fissile content. No single technique can provide all desired information, necessitating an approach using multiple detector systems and types. This paper presents our analysis of the Passive Neutron Albedo Reactivity Fission Chamber (PNAR-FC) detector system. PNAR-FC is a simplified version of the PNAR technique originally developed in 1997. This earlier research was performed with a high efficiency, {sup 3}He-based system (PNAR-3He) with which multiplicty analysis was performed. With the PNAR technique a portion of the spent fuel assembly is wrapped in a 1 mm thick cadmium liner. Neutron count rates are measured both with and without the cadmium liner present. The ratio of the count rate with the cadmium liner to the count rate without the cadmium liner is calculated and called the cadmium ratio. In the PNAR-3He technique, multiplicity measurements were made and the cadmium ratio was shown to scale with the fissile content of the material being measured. PNAR-FC simplifies the PNAR technique by using only a few fission chambers instead of many {sup 3}He tubes. Using a simplified PNAR-FC technique provides for a cheaper, lighter, and thus more portable detector system than was possible with the PNAR-3He system. The challenge with the PNAR-FC system are two-fold: (1) the change in the cadmium ratio is weaker as a afunction of the changing fissile content relative to multiplicity count rates, and (2) the efficiency for the fission chamber based system are poorer than for the {sup 3}He based detectors. In this paper, we present our research on using the PNAR-FC detector system to quantify the fissile content of a spent nuclear fuel assembly.},
doi = {},
url = {https://www.osti.gov/biblio/1015240},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 2010},
month = {Fri Jan 01 00:00:00 EST 2010}
}