Verification of MCNP simulation of neutron flux parameters at TRIGA MK II reactor of Malaysia.
Appl Radiat Isot
; 70(10): 2488-93, 2012 Oct.
Article
em En
| MEDLINE
| ID: mdl-22885391
ABSTRACT
A 3-D model for 1 MW TRIGA Mark II research reactor was simulated. Neutron flux parameters were calculated using MCNP-4C code and were compared with experimental results obtained by k(0)-INAA and absolute method. The average values of φ(th),φ(epi), and φ(fast) by MCNP code were (2.19±0.03)×10(12) cm(-2)s(-1), (1.26±0.02)×10(11) cm(-2)s(-1) and (3.33±0.02)×10(10) cm(-2)s(-1), respectively. These average values were consistent with the experimental results obtained by k(0)-INAA. The findings show a good agreement between MCNP code results and experimental results.
Texto completo:
1
Coleções:
01-internacional
Base de dados:
MEDLINE
Tipo de estudo:
Prognostic_studies
Idioma:
En
Revista:
Appl Radiat Isot
Assunto da revista:
MEDICINA NUCLEAR
/
SAUDE AMBIENTAL
Ano de publicação:
2012
Tipo de documento:
Article
País de afiliação:
Malásia