1 |
P.E. Warwick, I.W. Croudace, and R. Marsh, "Maintaining radioanalytical data quality: The challenges of decommissioning analysis", Nucl. Future, 7, 44-47 (2011).
|
2 |
A. Harms and C. Gilligan, "Development of a neutron-activated concrete powder reference material", Appl. Radiat. Isot., 68, 1471-1476 (2010).
DOI
|
3 |
S.M. Judge and P.H. Regan, "Radionuclide metrology research for nuclear decommissioning", Rad. Phys. Chem, 140, 463-465 (2017).
DOI
|
4 |
S. Parry, "Quality assurance in the nuclear sector", Radiochim. Acta, 100, 495-501 (2012).
DOI
|
5 |
D. Kim, I.W. Croudace, and P.E. Warwick, "The requirement for proper storage of nuclear anbd related decommissioning samples to safeguard accuracy of tritium data", J. Haz. Mater., 213-214, 292-298 (2012).
DOI
|
6 |
D. Kim, P.E. Warwick, and I.W. Croudace, "Tritium speciation in nuclear reactor bioshield concrete and its impact on accurate analysis", Anal. Chem., 80, 5476-5480 (2008).
DOI
|
7 |
I.W. Croudace, P.E. Warwick, and D. Kim, "Using thermal evolution profiles to infer tritium speciation in nuclear site metals: An aid to decommissioning", Anal. Chem., 86, 9177-9185 (2014).
DOI
|
8 |
X. Hou, "Determination of Ni and Fe in nuclear waste samples using radiochemical separation and liquid scintillation counting", Anal. Chim. Acta, 535, 297 -307 (2005).
DOI
|
9 |
I. W. Croudace, B.C. Russell, and P.E. Warwick, "Plasma source mass spectrometry for radioactive waste characterisation in support of nuclear decommissioning: a review", J. Anal. At. Spectrom., 32, 494-526 (2017).
DOI
|
10 |
X. Hou., "Rapid analysis of C and H in graphite and concrete for decommissioning of nuclear reactor", Appl. Radiat. Isot., 62, 871-882 (2005).
DOI
|
11 |
P.E. Warwick, I.W. Croudace, and D.J. Hillegonds, "Effective determination of the long-lived nuclide Ca in nuclear reactor bioshield concretes: Comparison of liquid scintillation counting and accelerator mass spectrometry", Anal. Chem., 81, 1901-1906 (2009).
DOI
|
12 |
D. Zapata-Garcia and H. Wershofen, "Development of radiochemical analysis strategies for decommissioning activities", Appl. Radiat. Isot., 126, 204-207 (2017).
DOI
|
13 |
C. Frechou and J-P Degros, "Measurement of Cl in nuclear wastes and effluents: validation of a radiochemical protocol with an in-house reference sample", J. Radioanal. Nucl. Chem., 263, 333-339 (2005).
DOI
|
14 |
P.E. Warwick and I.W. Croudace, "Measurement of Cd in irradiated cadmium shielding using liquid scintillation counting, In Mobius S., Noakes J. & Schonhofer F. LSC 2008, Advances in Liquid Scintillation Spectrometry", Radiocarbon, University of Arizona, USA (2009).
|
15 |
J. Qiao and X. Hou, "Frationation of plutonium in environmental and bio-shielding concrete samples using dynamic sequential extraction", J. Env. Rad., 101,, 244-249 (2010).
DOI
|
16 |
B. Bisplinghoff, M. Lochny, J. Fachinger, and H. Brucher, IAEA Technical Committee meeting : Nuclear graphite Waste Management, 153-159, October 18-20, 1999, Manchester, UK.
|
17 |
S. Dulanska, B. Remenec, J. Bilohuscin, L. Matel, and M. Bujdos, "Development of Sn separation method by means of anion exchange resin and gamma spectrometry", Appl. Radiat. Isot., 123, 128-132 (2017).
DOI
|
18 |
PNNL Inorganic and radiochemical analysis of AW-101 and AN-107 'diluted feed' materials, Pacific North-West National Laboratory, Washington, USA, Report PNWD-2463 Rev 1 (1999).
|