Simulation of criticality control in aqueous homogeneous reactor for Mo-99 production using MCNP
Creators
- 1. Nuclear Engineering Department, Faculty of Engineering, King Abdulaziz University, P.O.Box 80240 Jeddah (Saudi Arabia)
Description
Tc-99m is very useful radioisotope in medical diagnostic procedure. Tc- 99m is produced from Mo-99 decay. Mo-99 can be produced in the aqueous homogeneous reactor. MCNP was used to study the aqueous homogeneous reactor reactivity control. We varied the height of uranyl nitrate (20% enrichment) solution and calculated the keff using MCNP. We identified the uranyl solution height that produces slightly super critical condition. The insertion height of control rod was varied and the MCNP code was run to calculate keff to ensure the reactor can be safely controlled. The case when the reactor core is completely filled with fuel solution was studied, and it was shown that the control rods are able to shut down the reactor. From MCNP simulation, we confirm that this reactor can be operated safely for long periods. The criticality of the reactor can be maintained using two methods: control the height of the liquid solution to address slow reactivity changes and the control rods for transient reactivity changes. (authors)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the European Nuclear Conference - ENC 2014
- Imprint Pagination
- 1238 p.
- Journal Page Range
- p. 530-540
- Report number
- INIS-XE--15-ENC-2014
Conference
- Title
- European Nuclear Conference
- Acronym
- ENC 2014
- Dates
- 11-14 May 2014
- Place
- Marseille (France)
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- France
- INIS RN
- 46123248
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AQUEOUS HOMOGENEOUS REACTORS; CONTROL ELEMENTS; CRITICALITY; ENRICHMENT; FUEL SOLUTIONS; MOLYBDENUM 99; MONTE CARLO METHOD; REACTIVITY; REACTOR CORES; SIMULATION; TECHNETIUM 99; TRANSIENTS; URANYL NITRATES
- Descriptors DEC
- ACTINIDE COMPOUNDS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; DAYS LIVING RADIOISOTOPES; DISPERSIONS; ENERGY SOURCES; EVEN-ODD NUCLEI; FLUID FUELED REACTORS; FUELS; HOMOGENEOUS MIXTURES; HOMOGENEOUS REACTORS; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; LIQUID FUELS; LIQUID HOMOGENEOUS REACTORS; MATERIALS; MIXTURES; MOLYBDENUM ISOTOPES; NITRATES; NITROGEN COMPOUNDS; NUCLEAR FUELS; NUCLEI; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLUTIONS; TECHNETIUM ISOTOPES; URANIUM COMPOUNDS; URANYL COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Document available online at: http://www.euronuclear.org/events/enc/enc2014/transactions.htm; 9 refs.
- Secondary number(s)
- ENC--2014-A0076