A spectrometric system was developed for spent fuel burnup evaluations at the LVR-15 research reactor, which employed highly enriched (36%) IRT-2M-type fuel. Such a system allows the measurement of fission product axial distribution by measuring certain nuclides, such as Cs137, Cs134, and their ratios, respectively. Within the paper, a comparison between experimental data provided by the spectrometric system and calculations in operational code called NODER is provided.

References

1.
IAEA
,
2007
, “
Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition
,”
International Atomic Energy Agency
, Vienna.
2.
Kostal
,
M.
,
Svadlenkova
,
M.
,
Koleska
,
M.
,
Rypar
,
V.
, and
Milcak
,
J.
,
2015
, “
Comparison of Various Hours Living Fission Products for Absolute Power Density Determination VVER-1000 Mock-Up in LR-0 Reactor
,”
Appl. Radiat. Isotopes
, 105, pp. 264–272. 0969-804310.1016/j.apradiso.2015.08.037
3.
Kost’al
,
M.
,
Svadlenkova
,
M.
, and
Milcak
,
J.
,
2014
, “
The Application and Comparison of Zr-97 and Sr-92 in the Absolute Determination of the Contribution of Power Density and Cladding Activation in a VVER-1000 Mock-Up on the LR-0 Research Reactor
,”
Nucl. Instrum. Method. Phys. Res. Sec. A
,
738
(
Feb.
), pp.
87
92
.
4.
dos Santos
,
A.
,
Fanaro
,
L.
,
Silva
,
G.
, and
Mendonca
,
A.
,
2011
, “
The Experimental Determination and Evaluation of the Three-Dimensional Fission Density Distribution of the IPEN/MB-01 Research Reactor Facility for the IRPhE Project
,”
Ann. Nucl. Energy
,
38
(
2–3
), pp.
418
430
.
5.
Koleška
,
M.
,
Viererbl
,
L.
,
Marek
,
M.
,
Ernest
,
J.
,
Šunka
,
M.
, and
Vinš
,
M.
,
2016
, “
Determination of IRT-2M Fuel Burnup by Gamma Spectrometry
,”
Appl. Radiat. Isotopes
,
107
, pp.
92
97
.
6.
Antes
,
M.
, et al.,
2010
, “
Předprovozní Bezpečnostní Zpráva Reaktoru LVR-15
,”
Centrum výzkumu Řež
, Řež.
7.
Rozhikov
,
V.
,
Enin
,
A.
,
Alexandrov
,
A.
,
Tkachev
,
A.
,
Lambert
,
J.
, and
Kadyrzhanov
,
K.
,
2007
, “
Design and Manufacture of Fuel Assemblies for Russian Research Reactors
,”
Saf. Relat. Issues Spent Nucl. Fuel Storage
, pp.
95
105
.
8.
Koleška
,
M.
,
Brož
,
V.
,
Ernest
,
J.
,
Kysela
,
J.
,
Marek
,
M.
, and
Rychecký
,
J.
,
2011
, “
Completed Conversion of the LVR-15 Research Reactor
,”
33rd RERTR 2011 International Meeting on Reduced Enrichment for Research and Test Reactors
,
Argonne National Laboratory, RERTR Department
,
Santiago, Chile
.
9.
Koleska
,
M.
,
Viererbl
,
L.
, and
Marek
,
M.
,
2014
, “
Calibration of Spent Fuel Measurement Assembly
,”
Radiat. Phys. Chem.
,
104
(
Nov.
), pp.
420
423
.
10.
Koleska
,
M.
,
Viererbl
,
L.
, and
Marek
,
M.
,
2014
, “
Development of the MCNPX Model for the Portable HPGe Detector
,”
Radiat. Phys. Chem.
,
104
(
Nov.
), pp.
351
354
.
11.
Ernest
,
J.
,
2006
, “
Abstrakt výpočtového programu NODERRev.1
,” ,
ÚJV Řež
, Řež, Czech Republic.
12.
Chadwick
,
M.
, et al.,
2011
, “
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
,”
Nucl. Data Sheets
,
112
(
12
), pp.
2887
2996
.
13.
Pelowitz
,
D. B.
,
2011
,
MCNPX User’s Manual, Version 2.7.0
,
LANL
,
Los Alamos
.
14.
Koleška
,
M.
, et al.,
2015
, “
Capabilities of the LVR-15 Research Reactor for Production of Medical and Industrial Radioisotopes
,”
J. Radioanal. Nucl. Chem.
,
305
(
1
),
51
59
. 0236-573110.1007/s10967-015-4025-5
You do not currently have access to this content.