A simple gamma spectrometry method for evaluating the burnup of MTR-type HEU fuel elements

Author:

Makmal T.,Aviv O.,Gilad E.

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference54 articles.

1. Introduction to Nuclear Reactor Theory;Lamarsh,1966

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

3. ASTM C1769-15, Standard Practice for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup, ASTM International, West Conshohocken, PA, 2015.

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

5. Irradiated fuel measurements;Phillips,1991

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1. A Method to Estimate the Burnup Using Initial Enrichment, Cooling Time, Total Neutron Source Intensity and Gamma Source Activities in Spent Fuels;Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT);2023-09-30

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. Delayed fast neutron as an indicator of burn-up for nuclear fuel elements;Nuclear Engineering and Technology;2021-10

4. 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

5. Estimation of the Dose Rate of Spent Fuel-Related Components of Lingao Nuclear Power Plant Using ORIGEN2 and MCNP5;Wuhan University Journal of Natural Sciences;2019-01-11

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