Large Sample Neutron Activation Analysis: Correction for neutron and gamma attenuation

Nukleonika

Volumn 49, Issue 3, 2004, Pages 115-121

  Tzika, Faidra ^a,b   Stamatelatos, Ion E ^a   Kalef Ezra, John ^b   Bode, Peter ^c  

^a INSTITUTE OF NUCLEAR TECHNOLOGY AND RADIATION PROTECTION   (Greece)

^b UNIVERSITY OF IOANNINA   (Greece)

^c DELFT UNIVERSITY OF TECHNOLOGY   (Netherlands)

Author keywords

Gamma ray attenuation; MCNP code; Neutron activation analysis; Neutron self shielding

Indexed keywords

GERMANIUM;

CHEMICAL ANALYSIS; CONFERENCE PAPER; IRRADIATION; MONTE CARLO METHOD; NEUTRON ACTIVATION ANALYSIS; NEUTRON RADIATION; PROTON TRANSPORT; RADIATION ATTENUATION; SPECTROSCOPY;

EID: 4544283089     PISSN: 00295922     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Conference Paper

References (16)

1. Baas HW, Blaauw M, Bode P, De Goeij JJM (1999) Collimated scanning towards 3D-INAA of inhomogeneous large samples. Fresenius J Anal Chem 363:753-759
2. Blaauw M, Baas HW, Donze M (2003) Height-resolved large-sample INAA of a 1 m long, 13 cm diameter ditch-bottom sample. Nucl Instrum Meth A 505:512-516
3. Bode P, Lakmaker O, Van Aller P, Blaauw M (1998) Feasibility studies of neutron activation analysis with kilogram-size samples. Fresenius J Anal Chem 360:10-17
4. Bode P, Overwater RMW (1993) Trace element determinations in very large samples: a new challenge for neutron activation analysis. J Radioanal Nucl Chem 167:169-176
5. Briesmeister JF (ed) (2000) MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C. LA-13709-M. Los Alamos National Laboratory, Los Alamos, USA
6. Degenaar IH, Blaauw M, De Goeij JJM (2003) Correction for neutron self-shielding in large-sample prompt-gamma neutron activation analysis: determination of macroscopic neutron cross sections. J Radioanal Nucl Chem 257:467-470
7. Fleming RF (1982) Neutron self-shielding factors for simple geometries. Appl Radiat Isot 33:1263-1268
8. Hubbel JH, Seltzer SM (1995) Tables of X-ray mass attenuation coefficients and mass energy-absorption coefficients 1 keV to 20 MeV for elements Z=1 to 92 and 48 additional substances of dosimetric interest. NISTIR-5632
9. International Atomic Energy Agency (1970) Neutron fluence measurements. Technical Reports Series No 107. IAEA, Vienna
10. Meghreblian RV, Holmes DK (1960) Reactor analysis. McGraw-Hill Book Company Inc, New York
11. Overwater RMW, Bode P (1998) Computer simulations of the effects of inhomogeneities on the accuracy of large sample INAA. Appl Radiat Isot 8:967-976
12. Overwater RMW, Bode P, De Goeij JJM (1993) Gamma-ray spectroscopy of voluminous sources: corrections for source geometry and self-attenuation. Nucl Instrum Meth A 324:209-218
13. Overwater RMW, Bode P, De Goeij JJM, Hoogenboom JE (1996) Feasibility of elemental analysis of kilogram-size samples by instrumental neutron activation analysis. Anal Chem 68:341-348
14. Overwater RMW, Hoogenboom JE (1994) Accounting for the thermal neutron flux depression in voluminous samples for instrumental neutron activation analysis. Nucl Sci Eng 117:141-157
15. Shakir NS, Jervis RE (2001) Correction factors required for quantitative large volume INAA. J Radioanal Nucl Chem 248:61-68
16. Tzika F, Stamatelatos IE (2004) Thermal neutron self-shielding correction factors for large sample instrumental neutron activation analysis using the MCNP code. Nucl Instrum Meth B 213:177-181