Gamma-ray spectroscopy on irradiated MTR fuel elements

Terremoto, L.A.A.; Zeituni, Carlos A.; Perrotta, J.A.; Silva, J.E.R da

doi:10.1016/s0168-9002(00)00250-3

Cited by 36 publications

(22 citation statements)

References 8 publications

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“…ORIGEN 2.2 -is a point depletion and decay computer code used to simulate nuclear fuel cycles [11][12][13] . In this study,-ORIGEN 2.2 computer code was used to calculate burnup and depletion rates along with fission products isotopes activities of fuel elements.…”

Section: Origen Model Calculationsmentioning

confidence: 99%

“…A number of isotopic ratios and activities have been used as burnup monitors and cooling times 6,12,13 . These isotopic ratios or absolute activities in conjunction with operator-declared values or computer programs can be used to create calibration curves in order to predict cooling time and burnup of irradiated fuel nondestructively and in-situ 3,12,18 .…”

Section: Introductionmentioning

confidence: 99%

“…These isotopic ratios or absolute activities in conjunction with operator-declared values or computer programs can be used to create calibration curves in order to predict cooling time and burnup of irradiated fuel nondestructively and in-situ 3,12,18 . The starting point of our study was to use the isotopic ratios and absolute activity isotopes that were reported in the literature 14,15,5 .…”

Section: Introductionmentioning

confidence: 99%

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A feasibility and optimization study to determine cooling time and burnup of advanced test reactor fuels using a nondestructive technique

Navarro

2013

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Section: Origen Model Calculationsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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A feasibility and optimization study to determine cooling time and burnup of advanced test reactor fuels using a nondestructive technique

Navarro

2013

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“…A typical IEA-R1 fuel element has 18 plane parallel fuel plates, mounted mechanically between two lateral aluminium holders with grooves, and its overall dimensions are (7.6 X 8.0) cm and 88.0 cm high. Each fuel plate consists of an aluminium cladding and a meat where the nuclear fuel is located (Terremoto et al, 2000). Figure 3 presents the design of two types of cylindrical fuel elements used in the research reactor IPR-R1.…”

Section: Nuclear Research Reactors In Operationmentioning

confidence: 99%

Safety Studies and General Simulations of Research Reactors Using Nuclear Codes

Costa¹,

Reis²,

Silva³

et al. 2011

Nuclear Power - System Simulations and Operation

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“…With the purpose to measure burnup of fuel assemblies with shorter decay periods, it was decided to build an in-pool facility. The measurement of burnup using gamma spectroscopy technique after long decay period is very well known and 137 Cs as monitor gives reliable results [2], [3], [4], [5]. However, the same measurement with short decay periods (few days) produces serious difficulties in the treatment of the collected experimental data.…”

Section: Introductionmentioning

confidence: 99%

Burn up measurements of LEU fuel for short cooling times

H.A.

et al. 2008

J. Phys.: Conf. Ser.

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Abstract. The measurements presented in this work were made essentially at in-pool gammaspectrometric facility, installed inside of the secondary pool of the RECH-1 research reactor, where the measured fuel elements are under 2 meters of water. The main reason for using the in-pool facility was because of its capability to measure the burning of fuel elements without having to wait so long that is, with only 6 cooling days, which are the usual times between reactor operations. Regarding these short cooling times, this work confirms again the possibility of using the 95 Zr as a promising burnup monitor, in spite of the rough approximations used to do it. These results are statistically reasonable within the range calculated using codes. The work corroborates previous results, presented in Santiago de Chile [1], and it suggests future improvements in that way. IntroductionIn the near future, the RECH-1 research reactor will be completely converted to the use of LEU (19.75% of 235 U) fuel. The current reactor core loads 22 HEU (45% of 235 U) fuel assemblies fabricated by the UKAEA in Deanery, Scotland, and 12 LEU fuel assemblies fabricated by the Chilean Fuel Fabrication Plant (PEC). The meat composition of the experimental LEU fuel assembly is U 3 Si 2 -Al, whereas the HEU fuel assemblies have a meat composed by UAl x -Al. The first two LEU fuel assemblies were loaded in the reactor core in December 1998, and the second two in July 1999. LEU fuel assemblies have been gradually loaded in the core to replace HEU fuel assemblies which have reached the discharged burn-up. The total conversion of the RECH-1 reactor will be achieved during the first semester 2006. The first four LEU fuel assemblies loaded in the reactor core are supporting a local qualification program to know the behavior under irradiation of fuel assemblies fabricated by the PEC.In order to measure the fuel burnup of irradiated fuel assemblies, the CCHEN has two completely independent facilities using gamma spectroscopy technique: a hot cell facility and an in-pool facility described in earlier works [1], [2]. The first facility is mainly used to measure burn up of spent fuel assemblies with decay periods larger than three months. With the purpose to measure burnup of fuel assemblies with shorter decay periods, it was decided to build an in-pool facility. [5]. However, the same measurement with short decay periods (few days) produces serious difficulties in the treatment of the collected experimental data. The origin of these difficulties is the high activity generated by a large number of fission products of short life time, which increases the dead time and background reducing the quality of the statistics of the monitor [6], and in our experience submerging completely the 137 Cs under the background radiation, even with 4 months operation and 6 cooling days. Monitors like 95 Zr,

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Gamma-ray spectroscopy on irradiated MTR fuel elements

Cited by 36 publications

References 8 publications

A feasibility and optimization study to determine cooling time and burnup of advanced test reactor fuels using a nondestructive technique

A feasibility and optimization study to determine cooling time and burnup of advanced test reactor fuels using a nondestructive technique

Safety Studies and General Simulations of Research Reactors Using Nuclear Codes

Burn up measurements of LEU fuel for short cooling times

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