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Title: Simulation on reactor TRIGA Puspati core kinetics fueled with thorium (Th) based fuel element

Abstract

In confronting global energy requirement and the search for better technologies, there is a real case for widening the range of potential variations in the design of nuclear power plants. Smaller and simpler reactors are attractive, provided they can meet safety and security standards and non-proliferation issues. On fuel cycle aspect, thorium fuel cycles produce much less plutonium and other radioactive transuranic elements than uranium fuel cycles. Although not fissile itself, Th-232 will absorb slow neutrons to produce uranium-233 ({sup 233}U), which is fissile. By introducing Thorium, the numbers of highly enriched uranium fuel element can be reduced while maintaining the core neutronic performance. This paper describes the core kinetic of a small research reactor core like TRIGA fueled with a Th filled fuel element matrix using a general purpose Monte Carlo N-Particle (MCNP) code.

Authors:
;  [1]; ; ; ;  [2]
  1. Universiti Tenaga Nasional. Jalan Ikram-UNITEN, 43000 Kajang, Selangor (Malaysia)
  2. Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)
Publication Date:
OSTI Identifier:
22494518
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1704; Journal Issue: 1; Conference: iNuSTEC2015: International muclear science, technology and engineering conference 2015, Negeri Sembilan (Malaysia), 17-19 Aug 2015; Other Information: (c) 2016 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; DESIGN; HIGHLY ENRICHED URANIUM; MONTE CARLO METHOD; NUCLEAR POWER PLANTS; PLUTONIUM; PROLIFERATION; PUSPATI; RESEARCH REACTORS; SAFETY; SECURITY; SLOW NEUTRONS; THORIUM 232; THORIUM CYCLE; TRIGA TYPE REACTORS; URANIUM 233

Citation Formats

Mohammed, Abdul Aziz, E-mail: azizM@uniten.edu.my, Rahman, Shaik Mohmmed Haikhal Abdul, Pauzi, Anas Muhamad, E-mail: anas@uniten.edu.my, Zin, Muhamad Rawi Muhammad, Jamro, Rafhayudi, and Idris, Faridah Mohamad. Simulation on reactor TRIGA Puspati core kinetics fueled with thorium (Th) based fuel element. United States: N. p., 2016. Web. doi:10.1063/1.4940062.
Mohammed, Abdul Aziz, E-mail: azizM@uniten.edu.my, Rahman, Shaik Mohmmed Haikhal Abdul, Pauzi, Anas Muhamad, E-mail: anas@uniten.edu.my, Zin, Muhamad Rawi Muhammad, Jamro, Rafhayudi, & Idris, Faridah Mohamad. Simulation on reactor TRIGA Puspati core kinetics fueled with thorium (Th) based fuel element. United States. doi:10.1063/1.4940062.
Mohammed, Abdul Aziz, E-mail: azizM@uniten.edu.my, Rahman, Shaik Mohmmed Haikhal Abdul, Pauzi, Anas Muhamad, E-mail: anas@uniten.edu.my, Zin, Muhamad Rawi Muhammad, Jamro, Rafhayudi, and Idris, Faridah Mohamad. 2016. "Simulation on reactor TRIGA Puspati core kinetics fueled with thorium (Th) based fuel element". United States. doi:10.1063/1.4940062.
@article{osti_22494518,
title = {Simulation on reactor TRIGA Puspati core kinetics fueled with thorium (Th) based fuel element},
author = {Mohammed, Abdul Aziz, E-mail: azizM@uniten.edu.my and Rahman, Shaik Mohmmed Haikhal Abdul and Pauzi, Anas Muhamad, E-mail: anas@uniten.edu.my and Zin, Muhamad Rawi Muhammad and Jamro, Rafhayudi and Idris, Faridah Mohamad},
abstractNote = {In confronting global energy requirement and the search for better technologies, there is a real case for widening the range of potential variations in the design of nuclear power plants. Smaller and simpler reactors are attractive, provided they can meet safety and security standards and non-proliferation issues. On fuel cycle aspect, thorium fuel cycles produce much less plutonium and other radioactive transuranic elements than uranium fuel cycles. Although not fissile itself, Th-232 will absorb slow neutrons to produce uranium-233 ({sup 233}U), which is fissile. By introducing Thorium, the numbers of highly enriched uranium fuel element can be reduced while maintaining the core neutronic performance. This paper describes the core kinetic of a small research reactor core like TRIGA fueled with a Th filled fuel element matrix using a general purpose Monte Carlo N-Particle (MCNP) code.},
doi = {10.1063/1.4940062},
journal = {AIP Conference Proceedings},
number = 1,
volume = 1704,
place = {United States},
year = 2016,
month = 1
}
  • The Monte Carlo MVP code system was adopted for the Reaktor TRIGA PUSAPTI (RTP) core calculation. The code was developed by a group of researcher of Japan Atomic Energy Agency (JAEA) first in 1994. MVP is a general multi-purpose Monte Carlo code for neutron and photon transport calculation and able to estimate an accurate simulation problems. The code calculation is based on the continuous energy method. This code is capable of adopting an accurate physics model, geometry description and variance reduction technique faster than conventional method as compared to the conventional scalar method. This code could achieve higher computational speedmore » by several factors on the vector super-computer. In this calculation, RTP core was modeled as close as possible to the real core and results of keff flux, fission densities and others were obtained.« less
  • Spent fuel transfer cask is used to transfer a spent fuel from the reactor tank to the spent fuel storage or for spent fuel inspection. Typically, the cask made from steel cylinders that are either welded or bolted closed. The cylinder is enclosed with additional steel, concrete, or other material to provide radiation shielding and containment of the spent fuel. This paper will discuss the Conceptual Design of fuel transfer cask for Reactor TRIGA Puspati (RTP)
  • As a consequence of the accident at the Fukushima Dai-ichi Nuclear Power Plant in Japan, the safety aspects of the one and only research reactor (31 years old) in Malaysia need be reviewed. Based on this decision, Malaysian Nuclear Agency in collaboration with Atomic Energy Licensing Board and Universiti Kebangsaan Malaysia develop a Level-1 Probability Safety Assessment on this research reactor. This work is aimed to evaluate the potential risks of incidents in RTP and at the same time to identify internal and external hazard that may cause any extreme initiating events. This report documents the methodology in developing amore » Level 1 PSA performed for the RTP as a complementary approach to deterministic safety analysis both in neutronics and thermal hydraulics. This Level-1 PSA work has been performed according to the procedures suggested in relevant IAEA publications and at the same time numbers of procedures has been developed as part of an Integrated Management System programme implemented in Nuclear Malaysia.« less
  • Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its decommissioning sometime in the future, a ground basis of assessment and an elaborative project management need to be established, covering the entire process from termination of reactor operation to the establishment of final status, documented as the Decommissioning Plan. At international level, IAEA recognizes the absence of Decommissioning Plan as one of the factors hampering progress in decommissioning ofmore » nuclear facilities in the world. Throughout the years, IAEA has taken initiatives and drawn out projects in promoting progress in decommissioning programmes, like CIDER, DACCORD and R2D2P, for which Malaysia is participating in these projects. This paper highlights the concept of Decommissioning plan and its significances to the Agency. It will also address the progress, way forward and challenges faced in developing the Decommissioning Plan for the PUSPATI TRIGA Reactor. The efforts in the establishment of this plan helps to provide continual national contribution at the international level, as well as meeting the regulatory requirement, if need be. The existing license for the operation of PUSPATI TRIGA Reactor does not impose a requirement for a decommissioning plan; however, the renewal of license may call for a decommissioning plan to be submitted for approval in future.« less
  • In this paper, spent ion exchange resin generated from PUSPATI TRIGA reactor (RTP) in Malaysian Nuclear Agency were characterized based on the water content, radionuclide content and radionuclide leachability. The result revealed that the water content in the spent resin is 48%. Gamma spectrometry analysis indicated the presence of {sup 134}Cs, {sup 137}Cs, {sup 152}Eu, {sup 54}Mn, {sup 58}Co, {sup 60}Co and {sup 65}Zn. The leachability test shows a small concentrations (<1 Bq/l) of {sup 152}Eu and {sup 134}Cs were leached out from the spent resin while {sup 60}Co activity concentrations slightly exceeded the limit generally used for industrial wastewatermore » i.e. 1 Bq/l. Characterization of spent ion exchange resin sampled from RTP show that this characterization is important as a basis to immobilize this radioactive waste using geopolymer technology.« less