Depletion measurements using a new gamma transparency method of irradiated MTR-type fuel assemblies

Author:

Krakovich A.,Aviv O.,Danon L.,Ben-Meir K.,Yungrais Z.,Halfon S.,Hazenshprung N.,Neder I.

Funder

IAEA

Pazy Foundation

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference27 articles.

1. IAEA, Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition, IAEA-TECDOC-1547, 2007.

2. IAEA, Practices and developments in spent fuel burnup credit applications, IAEA-TECDOC-1378, 2003.

3. Dissolution and burnup determination of irradiated U-Zr alloy nuclear fuel by chemical methods;Kim;Nucl. Eng. Technol.,2006

4. ASTMC1769-15, Standard Practice for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup, ASTM International, West Conshohocken, PA, 2015.

5. EGADSNF, Spent nuclear fuel assay data for isotopic validation-State-of-the- art Report, Paris, France: OECD, NEA/NSC/WPNCS/DOC 5, 2011.

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2. High-Fidelity Monte Carlo Analysis of Highly-Localized Fission Power Peaking near a Flux Trap in an MTR Core;International Journal of Energy Research;2023-09-06

3. A code for simulating a high-resolution gamma-ray spectrum of a fission sample;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2020-07

4. Nondestructive measurements of residual 235U mass of Israeli Research Reactor-1 fuel using the Advanced Experimental Fuel Counter;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2020-06

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