Correction calculations for measure of the emission rate of the neutron sources in manganese sulfate bath at LNMRI/IRD
- 1. Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil). Programa de Pos-graduacao
- 2. Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil). Lab. Nacional de Metrologia das Radiacoes Ionizantes
Description
The Manganese Sulphate Bath [BSM] is the principal method used in laboratories of metrology to absolutely neutrons sources. The BSM consists basically of a big tank, full of manganese aqueous sulphate solution, next to the saturation condition. The radioactive source object of the measurement is immersed in the solution, where the majority of neutrons emitted by that is captured by the manganese, that it becomes radioactive [56Mn]. When decaying 56Mn emits radiation gamma, used in the measure of the emission rate of the neutron sources. Many parameters are used to correct the emission rate of the neutron source, amongst which are the losses due to neutron escape of the BSM, fast neutron capture for the solution and neutron capture by the source. The present work calculates these losses through Monte Carlo simulation [MCNP4C2]. In this simulation, the sources of routine used in the neutron lab at the Radiation Protection and Dosimetry have been considered [LN-IRD]. The objective of the simulation is to diminish the uncertainties and increase the accuracies on the determination of the mentioned losses. In simulation, it is possible to make individual calculations for each problem itself and determine all the components of the losses, for each specific situation of measurement. In future, the losses calculated by Monte Carlo method will substitute the ones that are currently used from experimental data. (author)
Additional details
Additional titles
- Original title (Portuguese)
- Calculo de correcoes da taxa de emissao de fontes de neutrons medida no sistema banho de sulfato de manganes do LNMRI/IRD
Publishing Information
- ISBN
- 85-99141-01-5
- Imprint Title
- Proceedings of the INAC 2005: International nuclear atlantic conference. Nuclear energy reducing global warming; 14. Brazilian national meeting on reactor physics and thermal hydraulics; 7. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [4886 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- International nuclear atlantic conference. Nuclear energy reducing global warming; 14. Brazilian national meeting on reactor physics and thermal hydraulics; 7. Brazilian national meeting on nuclear applications
- Acronym
- INAC 2005
- Dates
- 28 Aug - 2 Sep 2005
- Place
- Santos, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 36105580
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACCURACY; CALIBRATION; CAPTURE; COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; M CODES; MANGANESE SULFATES; MONTE CARLO METHOD; NAI DETECTORS; NEUTRON EMISSION; NEUTRON REACTIONS; NEUTRON SOURCES
- Descriptors DEC
- BARYON REACTIONS; CALCULATION METHODS; COMPUTER CODES; DATA; EMISSION; HADRON REACTIONS; INFORMATION; MANGANESE COMPOUNDS; MEASURING INSTRUMENTS; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUMERICAL DATA; OXYGEN COMPOUNDS; PARTICLE SOURCES; RADIATION DETECTORS; RADIATION SOURCES; SCINTILLATION COUNTERS; SIMULATION; SOLID SCINTILLATION DETECTORS; SULFATES; SULFUR COMPOUNDS; TRANSITION ELEMENT COMPOUNDS
Optional Information
- Notes
- 4 refs., 5 tabs., 1 photo. Code: 1532.pdf Imprint:Published only in CD-Rom