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Bolshinsky, Igor

Publications and source records attributed to Bolshinsky, Igor.

HEU Removal from MNSR Reactors

This artifact is a slide presentation about spent HEU core removal of a Chinese-built Miniature Neutron Source Reactor (MNSR). The presentation describes the Skoda VPVR/M cask in detail and the auxiliary equipment needed to safely remove the spent HEU and transport it. Removal activities of MNSR spent HEU from Ghana and Nigeria MNSRs, and air transport from these countries to China are discussed. The International MNSR Training Facility in Ghana is also mentioned.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Acceptance Test of WCTC with LEU Fuel at the IVG.1M Research Reactor Site in Kazakhstan

The water-cooled technological channels (WCTC) with low-enriched uranium (LEU) fuel, in the amount required for conversion, were delivered to the IVG.1M site by the manufacturer in February 2021 and thereafter the site acceptance test (SAT) of the WCTCs and the fuel elements started immediately. The paper provides an overview of the SAT conducted between March and November 2021 by the designated experts of the reactor operator and the manufacturer. It includes the introduction of the IVG.1M reactor and its unique WCTCs, and the inspection methodology to verify the conformity of the quality of the LEU fuel with the Technical Design (reference document). The paper presents results of the non-destructive and destructive tests, the outcomes of the thermohydraulic measurements, as well as the evaluation and corrective actions (if any), including the amendments (modifications) of the Technical Design initiated by the manufacturer based on the test results. Finally, the paper draws conclusions on the effectiveness of the SAT method used, captures consolidated experiential knowledge and shares lessons learned that can be used in general when planning and performing fuel verification.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DEVELOPMENT OF AN APPROACH FOR DOWNBLENDING AND DISPOSITION OF IRRADIATED GRAPHITE FUEL

The IGR reactor, a pulse-type test experimental reactor, reached full power in 1961. The reactor contains a center axial experimental ampoule that is subjected to a large pulse of neutrons (neutron flux maximum density of 7×1016 n/cm2·s, peak power 10GW) when the reactor is operated. The fuel form for the IGR reactor is graphite cubes and rods impregnated with highly enriched (90%) uranyl-dinitrate (UO2(NO3)2·6H2O). This fuel is eligible for return to Russia for reprocessing under the Russian Research Reactor Fuel Return program. However due to some technical and licensing issues it was decided to immobilize this fuel in Kazakhstan. The disposition approach thus selected for the spent HEU fuel involves down-blending of the fuel followed by cementation. Development of the process for down-blending and subsequent cementation requires a process that satisfies many criteria, including fissile content, compressive strength, permeability, and containment of radioactivity, among others. One key goal of the final product is to meet the criteria for termination of safeguards. This paper will describe the overall challenge associated with disposition of irradiated HEU graphite spent fuel, the identification of the objectives of the disposition process, and the constraints associated with development of the process and the waste form.

Gaines, Kris↗

International MNSR Training Center

Plans for the conversion of the Chinese origin miniature neutron source reactors (MNSRs) to low-enriched uranium (LEU), and the return of the high- enriched uranium (HEU) core to China, were initiated in February 2011 when an international MNSR Working Group (WG) was established to coordinate these activities. Based on a Ghana Atomic Energy Commission (GAEC) decision, the MNSR core at the GHARR-1 facility was selected for pilot shipment. Working on the preparation of the HEU MNSR materials’ removal from the GHARR-1 facility as a training tool, a mock-up MNSR vessel was built for operator training. Experiencing the usefulness of the mock-up vessel in operator training in the Ghana case has since been developed further into a full-scale training facility, named the International MNSR Training Center (IMTC), which is now available for training operators from MNSR operating countries. The main objective of this Book is to document the IMTC as a full-scale MNSR training facility in operator training for HEU MNSR core discharge and packaging. The goal is to describe the IMTC in its full complexity — that is: (1) to present the IMTC’s buildings with its internal and outer areas; (2) to provide a full listing of the installed equipment, as well as a functional description, available at the IMTC site; (3) to introduce the training materials, tutorials, and training program; and (4) to present the training sessions and Dry-run demonstration of the recently completed NIRR-1 operator training, with their experiences and lessons-learned included. This Book serves as a kind of user manual for the IMTC, which contains all of the information to launch training courses at the site at any time. The target audience for this Book is the MNSR community, especially MNSR operators and regulators who are facing HEU-LEU core conversion and HEU material transportation, who require operator training to carry out their jobs safely and professionally.

99 - GENERAL AND MISCELLANEOUS↗

IBR-2M Reactor Modeling with MCNP, SERPENT, CUBIT, and GIMP Computer Programs

IBR-2M is a fast research reactor located in Dubna (Russia), which operates in supercritical condition for ~800 μs every 200 ms. Two reflector parts are rotating in opposite directions generating 1.8 GWth peak power when the two parts align with the fuel zone. The reactor core uses plutonium fuel and sodium coolant. The control rods are located in stationary reflector zones. This report describes the computational modeling of the IBR-2M reactor. Two independent computational models were generated using MCNP and SERPENT computer programs. The MCNP model uses combinatorial geometry based on macro bodies, e.g. boxes, cylinders, hexagons, spheres, cones, etc., and surfaces. The SERPENT model is based on the STereo Lithographic (STL) geometry representation that is used by 3D printers. The STL geometry was constructed using the CUBIT computer program. The water cooling system of the stationary and the rotating reflectors has a very complicated geometry, involving serpentines and irregular surfaces profiles. The materials in these areas have been homogenized using the GIMP image editor according to the material distributions obtained from the colors of the design drawings. The MCNP and the SERPENT inputs consist of ~1500 and ~1750 lines, respectively. The calculated effective multiplication factors from these two Monte Carlo computer programs with different models agree within 50 pcm.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

International MNSR Training Center in Ghana Provides HEU Removal Expertise

Building on our years of cooperation, the United States and Ghana worked together to construct the International MNSR Training Center (IMTC) at the National Nuclear Research Institute of the Ghana Atomic Energy Commission (NNRI/GAEC) in Accra, Ghana. Here, the IMTC was used for training operators in Ghana to discharge the reactor’s HEU core, load it into a shielded transportation cask, and secure the cask for transport. Moving forward, the IMTC will be used to train personnel from the remaining countries with MNSRs to conduct these operations.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Initial Shipment of MNSR Reactor HEU Spent Nuclear Fuel from Ghana to China

The repatriation of Russian and US origin fresh and spent, high enriched uranium (HEU) research reactor fuel has been conducted since 1996. In 2006, efforts were initiated to convert Chinese designed Miniature Neutron Source Reactors (MNSRs) from HEU to low enriched uranium (LEU) fuel. The Ghana Research Reactor-1 (GHARR-1) is the first of five such MNSR reactors outside of China eligible for conversion and fuel return to China. Under a project involving China and Ghana as operating country, as well as the U.S.A and the IAEA the HEU core is to be repatriated to China and a new LEU core is to be installed. The present paper discusses the preparation of the HEU core for removal, describing the logistics of the shipment of the HEU core and the lessons learned which can be applied to the remaining MNSR shipments.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗