Research reactor model for isotope production based on the design of VVER-440 reactors

Abstract The following work is an attempt to develop a model research reactor based on VVER-440 technologies, primarily for the production of radioisotopes used in nuclear medicine procedures. The article describes the basic design features of the model 10 MW multipurpose VVR reactor, including the features of reactor fuel, core, and related structures. A comparative analysis of targets for maximizing 99Mo production is also presented.

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Sensitivity and Uncertainty Information Incorporated Loss of Flow Accident Analyses for Research Reactors

Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation ◽

10.1115/icone2020-16242 ◽

2020 ◽

Author(s):

Tao Liu ◽

Zeyun Wu

Keyword(s):

Research Reactor ◽

Safety Analysis ◽

Primary Objective ◽

Analysis Procedure ◽

System Level ◽

Normal Operation ◽

Reactor Model ◽

Research Reactors ◽

Design Basis ◽

Uncertainty Information

Abstract This paper outlines a system level safety analysis procedure for research reactors incorporating sensitivity and uncertainty components. The protected loss of flow (LOF) accident was selected as an exemplified design basis accident to demonstrate the analysis procedure. The conceptual NIST (National Institute of Standards and Technology) horizontally split-core based research reactor was adopted as a research reactor model in the study. Two system level dynamics codes, RELAP5-3D and PARET, were employed in this work in a comparison study manner. The primary objective of the present work is to demonstrate the analysis capability of integrating sensitivity and uncertainty information in addition to traditional predictions of the system code models for the study of the thermal-hydraulics (T/H) safety characteristics of research reactors under accidental transient scenarios. The canonical transient predictions on the LOF accident yielded from the two system codes mentioned above have demonstrated some noticeable yet acceptable discrepancies. To better understand the discrepancies observed in the simulations, sensitivity and uncertainty analyses were performed by coupling the RELAP5-3D model and the data analytic engines provided by the RAVEN framework developed by INL. The sensitivity information reveals the significances of key figure of merits such as the peak cladding temperature varies with different boundary and initial parameters in both normal operation and design basis transients. The uncertainty analysis informs the deviations of the responses contributed by the errors of various input components. Both the sensitivity and uncertainty information will be incorporated into a safety analysis framework as part of the safety characteristic predictions delivered by the framework.

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Using Monte Carlo transport to accurately predict isotope production and activation analysis rates at the University of Missouri research reactor

Journal of Radioanalytical and Nuclear Chemistry ◽

10.1007/s10967-009-0163-y ◽

2009 ◽

Vol 282 (1) ◽

pp. 255-259 ◽

Cited By ~ 3

Author(s):

N. J. Peters ◽

J. D. Brockman ◽

J. D. Robertson

Keyword(s):

Monte Carlo ◽

Activation Analysis ◽

Research Reactor ◽

Isotope Production ◽

University Of Missouri ◽

The University ◽

Monte Carlo Transport

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TRIGA PUSPATI reactor: model analysis and accuracy

Indonesian Journal of Electrical Engineering and Computer Science ◽

10.11591/ijeecs.v20.i2.pp788-797 ◽

2020 ◽

Vol 20 (2) ◽

pp. 788

Author(s):

Nor Arymaswati Abdullah ◽

Azura Che Soh ◽

Samsul Bahari Mohd Noor ◽

Ribhan Zafira Abd. Rahman ◽

Julia Abd Karim

Keyword(s):

Simulation Model ◽

Research Reactor ◽

Reactor System ◽

Good Representation ◽

Reactor Model ◽

The Real ◽

Control Console ◽

Verification Methods ◽

And Control ◽

Real Plant

<p>There are many challenging issues with research reactor, such as time variation and uncertainty. Since its first criticality in 1982, the biggest changes in TRIGA PUSPATI Reactor system is the replacement of instrumentation and control console system from analogue to digital in 2013. Apart from providing methods of controlling the power reactor via the control rod movement, the Instrumentation and Control Console System also provides monitoring and display for all reactor parameters to protect the reactor from undue influences or abnormal circumstances. Meanwhile, the simulation model of the TRIGA PUSPATI Reactor system has been developed in the Simulink-MATLAB. The simulation model development is based on the research reactor mathematical representatives and the real plant parameters of TRIGA PUSPATI Reactor. However, the performance of this simulation model needs to be evaluated. Since there is no report or paper work found on the performance of the simulation model to represent the real system of RTP, the present study aims to carry out an analysis for more rigorous understanding of the TRIGA PUSPATI Reactor model simulation through validation and verification methods. After analysing the result, it was found that the simulation model has a good representation of a real plant.</p>

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Conceptual Nuclear Design of a 20 MW Multipurpose Research Reactor

Nuclear Science and Technology ◽

10.53747/jnst.v4i1.210 ◽

2014 ◽

Vol 4 (1) ◽

pp. 26-35

Author(s):

Nhi Dien Nguyen ◽

Ton Nghiem Huynh ◽

Vinh Vinh Le ◽

Hai Dang Vo Doan ◽

Chulgyo Seo ◽

...

Keyword(s):

Power Distribution ◽

Research Reactor ◽

Design Parameters ◽

Reactor Model ◽

Control Rod ◽

Reactivity Coefficients ◽

And Performance ◽

Fuel Meat ◽

New Research ◽

Pool Type

This paper presents some of studied results of a pre-feasibility project on a new research reactor for Vietnam. In this work, two conceptual nuclear designs of 20 MW multi-purpose research reactor have been done. The reference reactor is the light water cooled and heavy water reflected open-tank-in-pool type reactor. The reactor model is based on the experiences from the operation and utilization of the HANARO. Two fuel types, rod and flat plate, with dispersed U3Si2-Al fuel meat are used in this study for comparison purpose. Analyses for the nuclear design parameters such as the neutron flux, power distribution, reactivity coefficients, control rod worth, etc. have been done and the equilibrium cores have been established to meet the requirements of nuclear safety and performance.

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