ISTC Projects

ISTC projects, managed by NTSC

K-437 «Application of Structural Materials Data from the BN-350 Fast Reactor to Life Extension of Light Water Reactors»

In the first task irradiation conditions will be calculated for candidate blanket assemblies to establish the axial distribution of operating temperature of the ducts, and the axial distribution of dpa/sec and fluence. MAEC and NTSC will perform this task, with guidance from ANL. The second task will involve machining the parts of the ducts from blanket assemblies and cutting out specimens from them at appropriate locations in the MAEC hot cells. The third task will involve the packaging and transportation of specimens between Aktau and the NNC facilities in Alatau; this small task will be shared between MAEC and NNC to ensure specimen activities (sizes) are compatible with the NNC facilities. The forth task will involve determination of swelling in the samples and will be performed in MAEC and NNC laboratories. This task includes profilometry of the ducts, sample preparation for density measurements and electron microscopy, and also implementation of corresponding investigations. Additionally, phase-structure investigations and mass-spectrometric determination of the impurities doped to radiation resistant steels can be performed. The fifth task will be devoted to investigation of the mechanical property changes as a result of reactor irradiation.

MAEC will perform “preliminary” mechanical tensile tests, while NNC will perform “precision” mechanical tensile and bending tests. Besides, optical metallography and electron microscopy will be applied. The sixth task will determine the gas content of samples using thermal desorption spectroscopy; this task will be performed by IETP specialists. The seven task will be devoted to the analysis of the results of complex investigations to predict the steels behavior under LWR irradiation conditions over a long period of time. This final task will be performed by all the participants of the project including ANL and EdF.

Similar work is being performed by ANL scientists on equivalent steel samples removed from the blanket region of the EBR-II fast reactor in Idaho. The inlet temperature of EBR-II was, however, 370 °C, requiring some extrapolation to LWR operating conditions. The proposed work in Kazakhstan is likely to greatly benefit from a comparison of results obtained at ANL. Collaboration with EdF is seen as bringing the needs and experience of the commercial nuclear sector to bear on the required work. It could be that details of the final workscope depend on the input of such a commercial enterprise.

Both ANL and EdF will participate in the analyses of the comprehensive research results for duct materials of BN-350 reactor fuel assemblies to predict materials behavior for a long-term irradiation in light water reactors.

K-512, Stage 1 «Develop, Install, and Operate a Cesium Trap, Based on the U.S. Technologies, to Reduce Cesium Levels in the BN-350 Primary Sodium and Enhance Plant Fire Protection Capabilities to Support Cesium Trap Operation»

The technical objective of this proposal is to implement the design concepts previously developed and install and operate a cesium trap at the BN-350 in order to lower the existing cesium concentration to the lowest practical level. Concomitant with this, appropriate fire protection enhancements will be made. Cesium Levels achieved at the EBR II (about 1.0 x 10-2 µCi/g) have been shown to be adequate. The objective is further to document the results of the work so that others decommissioning sodium cooled reactors may benefit form the experience gained.

K-512, Stage 2 “Handling with spent cesium traps for following disposal” 

The technical objective of this proposal is to implement the design concepts previously developed and install and operate a cesium trap at the BN-350 in order to lower the existing cesium concentration to the lowest practical level. Concomitant with this, appropriate fire protection enhancements will be made. Cesium Levels achieved at the EBR II (about 1.0 x 10-2 µCi/g) have been shown to be adequate. The objective is further to document the results of the work so that others decommissioning sodium cooled reactors may benefit form the experience gained.

К-513 “Preparation of a Decommissioning Plan for International Review to Place the BN-350 Reactor in a SAFESTOR Condition”

The technical objective of this joint U.S. – Kazakhstan collaborative work is to create a concise plan meeting international standards of excellence to place the BN-350 reactor plant in safe-storage condition. The quality and content of the plan should be such that it will be successfully reviewed and credited by an international peer panel of experts. The intent of the plan is to provide a clear picture of the tasks required to place the BN-350 in SAFESTOR so that other international donors can make confident decisions as to where they can contribute in a meaningful way to support the plant’s decommissioning. In this regard, technical concepts must be developed in parallel for near-term key tasks for placing the plant in safe storage — tasks such as sodium draining and processing.

K-969 “Design and Development of a Scaled-Down Simulation Complex of Automated Control and Dataware System for BN-350 Sodium Coolant Processing Workflow”

Design and development of a scaled-down simulation complex of automated control and dataware system for BN-350 sodium coolant processing workflow will allow solving a package of technical issues related to processing technology, synthesis of control algorithms, information processing and granting, workflow management operational schemes testing, emergency analysis, and operating personnel training. The order of the project implementation is presented in tasks below.

K-970 “Development of Experimental-Industrial Technology of Radioactive Waste Processing into Geocement Stone and Equipment for its Realization”

The technical objective of this work is experimental checking of the technological possibility to process sodium hydroxide into geocement stone using raw materials available in Kazakhstan. At that characterization of available raw materials, their physical-mechanical behavior and chemical composition, elaboration of the optimal mixture of components, regimes and requirements to the equipment and also certification of the final product will be performed. The experimental equipment will be developed, manufactured and assembled; the whole technological cycle will be worked through up to obtaining of certified final product acceptable for disposal.

K-1006 “Development of off-gas system for SPF”

Design and development of different-purpose technological systems are connected with existing technology study, selection of system functional scheme, calculations of technological process in accordance with selected structural scheme, selection of standard and non-standard equipment, construction of separate technology components and equipment type connections.

K-1199 “Development of Alternate technologies for GCS” 

K-1345 “Removal of Na and NA-K residuals from the vessel and circuits of BN-350” 

K-1583 “Survey of hot cell disposal of BN-350 reactor”

K-2057  Treatment and Safe Disposal of Liquid Radioactive Waste