PMID- 24294545
OWN - NLM
STAT- PubMed-not-MEDLINE
DCOM- 20131202
LR  - 20211021
IS  - 2193-1801 (Print)
IS  - 2193-1801 (Electronic)
IS  - 2193-1801 (Linking)
VI  - 2
DP  - 2013
TI  - Proposed design for the PGAA facility at the TRIGA IPR-R1 research reactor.
PG  - 597
LID - 10.1186/2193-1801-2-597 [doi]
LID - 597
AB  - BACKGROUND: This work presents an initial proposed design of a Prompt Gamma 
      Activation Analysis (PGAA) facility to be installed at the TRIGA IPR-R1, a 
      60 years old research reactor of the Centre of Development of Nuclear Technology 
      (CDTN) in Brazil. The basic characteristics of the facility and the results of 
      the neutron flux are presented and discussed. FINDINGS: The proposed design is 
      based on a quasi vertical tube as a neutron guide from the reactor core, inside 
      the reactor pool, 6 m below the room's level where shall be located the rack 
      containing the set sample/detector/shielding. The evaluation of the thermal and 
      epithermal neutron flux in the sample position was done considering the 
      experimental data obtained from a vertical neutron guide, already existent in the 
      reactor, and the simulated model for the facility. METHODS: The experimental 
      determination of the neutron flux was obtained through the standard procedure of 
      using Au monitors in different positions of the vertical tube. In order to 
      validate both, this experiment and calculations of the simulated model, the flux 
      was also determined in different positions in the core used for sample 
      irradiation. The model of the system was developed using the Monte Carlo code 
      MCNP5. CONCLUSION: The preliminary results suggest the possibility of obtaining a 
      beam with minimum thermal flux of magnitude 10(6) cm(-2) s(-1), which confirm the 
      technical feasibility of the installation of PGAA at the TRIGA IPR-R1 reactor. 
      This beam would open new possibilities for enhancing the applications using the 
      reactor.
FAU - Guerra, Bruno T
AU  - Guerra BT
AD  - Department of Nuclear Engineering (DEN), Federal University of Minas Gerais 
      (UFMG), Av. Antonio Carlos 6627, CEP, 31270-901 Belo Horizonte, Brazil ; 
      Department of Nuclear Engineering (DEN), Federal University of Minas Gerais 
      (UFMG), Av. Antonio Carlos 6627, CEP, 31270-901 Belo Horizonte, Brazil.
FAU - Jacimovic, Radojko
AU  - Jacimovic R
FAU - Menezes, Maria Angela Bc
AU  - Menezes MA
FAU - Leal, Alexandre S
AU  - Leal AS
LA  - eng
PT  - Journal Article
DEP - 20131109
PL  - Switzerland
TA  - Springerplus
JT  - SpringerPlus
JID - 101597967
PMC - PMC3833902
OTO - NOTNLM
OT  - CDTN (Centre for Development of Nuclear Technology)
OT  - NAA (Neutron Activation Analysis)
OT  - Neutron activation analysis TRIGA IPR-R1
OT  - PGAA (Prompt Gamma Activation Analysis)
OT  - PGAA facility
EDAT- 2013/12/03 06:00
MHDA- 2013/12/03 06:01
PMCR- 2013/11/09
CRDT- 2013/12/03 06:00
PHST- 2013/05/16 00:00 [received]
PHST- 2013/10/29 00:00 [accepted]
PHST- 2013/12/03 06:00 [entrez]
PHST- 2013/12/03 06:00 [pubmed]
PHST- 2013/12/03 06:01 [medline]
PHST- 2013/11/09 00:00 [pmc-release]
AID - 651 [pii]
AID - 10.1186/2193-1801-2-597 [doi]
PST - epublish
SO  - Springerplus. 2013 Nov 9;2:597. doi: 10.1186/2193-1801-2-597. eCollection 2013.