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Cooperative MPC&A Enhancements at Russian Navy Sites

Description: U.S. MPC&A cooperation with the Russian Federation (RF) Navy is based on a Joint Statement signed in 1996 to protect Highly Enriched Uranium (HEU) fresh fuel used for nuclear propulsion. The Russian Federation Navy is the largest owner in Russia of highly enriched uranium, both in the form of fresh nuclear fuel, and in the form of slightly irradiated fuel with a long cooling time after irradiation. As a result of this agreement, projects began at the Northern Fleet Fresh Fuel Storage Facili… more
Date: May 30, 2001
Creator: Nelson, N. N.; O'Shell, P.; Hendrickson, S.; Sukhoruchkin, V.; Antipov, S.; Melkhov, E. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Dry Blending to Achieve Isotopic Dilution of Highly Enriched Uranium Oxide Materials

Description: The end of the cold war produced large amounts of excess fissile materials in the United States and Russia. The Department of Energy has initiated numerous activities to focus on identifying material management strategies for disposition of these excess materials. To date, many of these planning strategies have included isotopic dilution of highly enriched uranium as a means of reducing the proliferation and safety risks. Isotopic dilution by dry blending highly enriched uranium with natural an… more
Date: April 1, 2001
Creator: Henry, Roger Neil; Chipman, Nathan Alan & Rajamani, R. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Oak Ridge Multiple Attribute System (ORMAS) for Pu, HEU, HE, Chemical Agents, and Drugs

Description: The concept for the Oak Ridge Multiple Attribute System (ORMAS) is a Nuclear Materials Identification System (NMIS) time-dependent coincidence processor that incorporates gamma ray spectrometry and utilizes a small, lightweight, portable DT neutron (14.1 MeV) generator (1 x 10{sup 8} n/s), proton recoil scintillation detectors, and a gamma ray detector (HPGe). ORMAS is based on detecting fission neutrons and gamma rays from inherent source fission, fission induced by the external DT source, gam… more
Date: September 21, 2001
Creator: Mihalczo, J.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ATR LEU Monothlic and Dispersed with 10B Loading Minimization Design – Neutronics Performance Analysis

Description: The Advanced Test Reactor (ATR), currently operating in the United States, is used for material testing at very high neutron fluxes. Powered with highly enriched uranium (HEU), the ATR has a maximum thermal power rating of 250 MWth. Because of the large test volumes located in high flux areas, the ATR is an ideal candidate for assessing the feasibility of converting HEU driven reactor cores to low-enriched uranium (LEU) cores. The present work investigates the optimized LEU Monolithic and Dispe… more
Date: October 1, 2001
Creator: Chang, G. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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NMIS Experience for Facility-To-Facility Transfer

Description: One of the applications of template matching for arms control/warhead dismantlement transparency regimes is for monitoring facility-to-facility transfers. In 1999, three highly enriched uranium (HEU) weapons components for which the Nuclear Materials Identification System (NMIS) signatures had been obtained at the shipper's site were received at the Y-12 National Security Complex. The NMIS signatures obtained upon receipt of these items were compared with those at the shipper's site t… more
Date: June 14, 2001
Creator: Mattingly, J. K.; Chiang, L. G.; Mullens, J. A. & Mihalczo, J. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Water-Reflected 233U Uranyl Nitrate Solutions in Simple Geometry

Description: A number of critical experiments involving {sup 233}U were performed in the Oak Ridge National Laboratory Building 9213 Critical Experiments Facility during the years 1952 and 1953. These experiments, reported in Reference 1, were directed toward determining bounding values for the minimum critical mass, minimum critical volume, and maximum safe pipe size of water-moderated solutions of {sup 233}U. Additional information on the critical experiments was found in the experimental logbooks. Two ex… more
Date: August 15, 2001
Creator: Elam, K.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Measurement Methodology of the Fissile Mass Flow Monitor for the HEU Transparency Implementation Instrumentation in Russia

Description: The highly enriched uranium (HEU) Transparency Agreement between the U.S. and Russian Federation (RF) requires implementation of transparency measures in the Russian facilities that are supplying product low enriched uranium (LEU) to the U.S. from down blended weapon-grade HEU material. To satisfy the agreement's non-proliferation objectives, the U.S. DOE is implementing the fissile mass flow monitor (FMFM) instrumentation developed by Oak Ridge National Laboratory. The FMFM provides unattended… more
Date: June 28, 2001
Creator: Uckan, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ANALYSIS OF THE SECOND ZEUS CRITICAL EXPERIMENT

Description: The Zeus experiments have been designed to test the adequacy of {sup 235}U cross sections in the intermediate energy range. The first Zeus experiment achieved initial criticality on April 26, 1999 with 10 HEU platters and 79 platters of graphite. The second experiment reached a critical condition on October 24, 2000, with 9 HEU platters and 54 platters of graphite. The first experiment, which has been described and analyzed previously, had a C/{sup 235}U ratio of approximately 52:1. The corresp… more
Date: January 1, 2001
Creator: MOSTELLER, R. & JAEGERS, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Sensitivity of Subcritical Measurement Simulations to Neutron Cross-Section Data

Description: Evaluation of nuclear data typically includes validation of the data through computation of k{sub eff}for critical assemblies. The sensitivity of the computed k{sub eff} values to the nuclear data is used as an indicator in determining the adequacy of an evaluation. Subcritical measurements offer an alternative to critical experiments as a means to evaluate nuclear data through direct computation of subcritical measurement quantities. In some instances, the subcritical measurement quantities ar… more
Date: August 24, 2001
Creator: Valentine, T.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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