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235U Determination using In-Beam Delayed Neutron Counting Technique at the NRU Reactor

Conference ·
OSTI ID:1226894
 [1];  [2];  [3];  [2];  [3];  [2];  [2];  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Canadian Nuclear Labs., Chalk River, ON (Canada)
  3. Royal Military College of Canada, Kingston, ON (United States)
+ Show Author Affiliations

This paper describes a collaborative effort that saw the Royal Military College of Canada (RMC)’s delayed neutron and gamma counting apparatus transported to Canadian Nuclear Laboratories (CNL) for use in the neutron beamline at the National Research Universal (NRU) reactor. Samples containing mg quantities of fissile material were re-interrogated, and their delayed neutron emissions measured. This collaboration offers significant advantages to previous delayed neutron research at both CNL and RMC. This paper details the determination of 235U content in enriched uranium via the assay of in-beam delayed neutron magnitudes and temporal behavior. 235U mass was determined with an average absolute error of ± 2.7 %. This error is lower than that obtained at RMCC for the assay of 235U content in aqueous solutions (3.6 %) using delayed neutron counting. Delayed neutron counting has been demonstrated to be a rapid, accurate, and precise method for special nuclear material detection and identification.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
NSERC
DOE Contract Number:
AC52-06NA25396
OSTI ID:
1226894
Report Number(s):
LA-UR--15-24339
Country of Publication:
United States
Language:
English

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Related Subjects

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
AQUEOUS SOLUTIONS
COUNTING TECHNIQUES
DATA COVARIANCES
DELAYED NEUTRONS
DETECTION
ENRICHED URANIUM
FISSILE MATERIALS
ISOTOPE RATIO
MASS
NEUTRON BEAMS
NEUTRON EMISSION
NRU REACTOR
URANIUM 235
neutron beamline
delayed neutron counting