Comparison of the effects of cadmium-shielded irradiation channel and a boron carbide-shielded irradiation channel of the outer irradiation channel of the Ghana research reactor-1 using MNCP
Creators
- 1. University of Ghana, Graduate School of Nuclear and Allied Sciences, P.O Box AE1, Atomic Energy, Accra, (Ghana)
- 2. Ghana Atomic Energy Commission, National Nuclear Research Institute, P.O Box LG80, Legon (Ghana)
Description
The MCNP model for the Ghana Research Reactor-1 (GHARR-1) was redesigned to incorporate cadmium-shielded irradiation channel as well as boron carbide-shielded channel in one of the outer irradiation channels. Further investigations were made to consider the boron carbide-shielded channel and both results were compared to determine the best material for the shielded channel. Before arriving at the final design of only one shielded outer irradiation channel, extensive investigations were made into several other possible designs. The concept of redesigning a new MCNP model which has a shielded channel is to equip GHARR-1 with the means of performing efficient epithermal neutron activation analysis. After the simulation, a comparison of the results from the boron carbide-shielded channel model for GHARR-1 and the epicadmium shielded channel was made. The Keff of the boron carbide-shielded channel model was recorded as 1.00282±0.00008 while that or the epicadmium designed model was recorded as 1.00332±0.00008. A prompt neutron lifetime of 1.5237x10-4s was recorded for the cadmium designed model while a value of 1.5245x10-4s was recorded for the boron carbide-shielded design of GHARR-l. The neutron energy causing fission for the boron carbide-shielded design of GHARR-1 was 1.3533x10-2MeV while that of the cadmium designed model was 1.3513x10-2MeV.
Availability note (English)
Available from Nigeria Atomic Energy Commission, 9 Kwame Nkrumah Crescent Asokoro, P.M.B. 646 Garki Abuja (NG)Additional details
Publishing Information
- Imprint Pagination
- [15 p.]
Conference
- Title
- 6. African conference on research reactor utilization and safety
- Dates
- 2-3 Nov 2009
- Place
- Abuja (Nigeria)
INIS
- Country of Publication
- Nigeria
- Country of Input or Organization
- Nigeria
- INIS RN
- 41079614
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BORON CARBIDES; CADMIUM; COMPARATIVE EVALUATIONS; EXPERIMENTAL CHANNELS; GHARR-1 REACTOR; MONTE CARLO METHOD; PERFORMANCE TESTING; SHIELDING MATERIALS
- Descriptors DEC
- BORON COMPOUNDS; CALCULATION METHODS; CARBIDES; CARBON COMPOUNDS; ELEMENTS; ENRICHED URANIUM REACTORS; EVALUATION; MATERIALS; METALS; MNSR TYPE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS