Long-lived activation products in reactor materials

Evans, J. C.; Lepel, E.L.; Sanders, R.W.; Wilkerson, C.L.; Silker, W.B.; Thomas, C.W.; Abel, Kenneth; Robertson, D.R.

doi:10.2172/6776358

Cited by 47 publications

(55 citation statements)

References 1 publication

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“…The first was that the concentrations of activation products be larger than or comparable to the concentration of fission products generated from impurity uranium in the materials. The contents of impurity uranium in Zircaloy-2 and SUS304 stainless steel were 0.00035 wt% and 0.0001 wt% [5], respectively. This value in INCONEL alloy is unknown.…”

Section: Target Nuclides Of Sensitivity Analysesmentioning

confidence: 96%

Sensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure Materials

Yamamoto

Okumura

Kojima

et al. 2014

Nuclear Back-End and Transmutation Technology for Waste Disposal

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Sensitivity analyses of initial compositions and cross sections were conducted to quantitatively clarify the source elements and the nuclear reactions dominating the generation of activation products. In these analyses, the ORI-GEN2.2 code was used with ORLIBJ40, a set of the cross-section libraries based on JENDL-4.0. Analyses were conducted for the activations of cladding tubes, end plugs, and spacers of fuel assemblies and channel boxes in BWR that are composed of zirconium alloy, stainless steel, and nickel-chromium-based alloy. From about 50 representative radioactive nuclides, several nuclides were selected as the targets of sensitivity analyses for the aspect of their large concentrations in the target materials.The results of sensitivity coefficients clarified the source elements and the nuclear reactions dominating the generation of activation products even for the nuclides generated through complicated pathways. These results could be utilized to select the objectives of the impurity elements for measurements and of nuclear data for the improvement of accuracy. These results will contribute to improvements in the accuracy of numerical evaluations of activation product concentrations.

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Section: Target Nuclides Of Sensitivity Analysesmentioning

confidence: 96%

Sensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure Materials

Yamamoto

Okumura

Kojima

et al. 2014

Nuclear Back-End and Transmutation Technology for Waste Disposal

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show abstract

“…The concrete is a composition of four components blended in a certain proportion: cement, crushed stones, sand, and water. The main weight compositions of concrete are calcium (41.6%), silicon (11.0%), aluminum (2.3%), iron (2.2%), sulfur (1.4%), potassium (0.56%), phosphorus (0.6%) and sodium (0.08%) [9]. The weight compositions of hydrogen, the carbon, and oxygen are not measured.…”

Section: Experiments In 10 and 15 MV Linacsmentioning

confidence: 99%

Estimation of neutron and gamma radiation doses inside the concrete shield wall for 10 and 15 MV medical linear accelerators

Obara¹,

Nakajima

Kitaura

et al. 2014

Progress in Nuclear Science and Technology

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High-energy electron linear accelerators (linacs) are used in radiotherapy for tumor treatment. By operating at electron energies above the thresholds of the (γ, n) photonuclear reaction, undesirable photoneutrons and radioisotopes are generated by high-energy x-rays. These photonuclear reactions occur on the linac accelerator head components, which are made from various materials. In these reactions, one can assume that secondary neutrons are dispersed all over the treatment rooms. The present work observed ambient dose equivalent of photon and neutron, and number of etch pits of wide-energy range Neupit produced by thermal and fast neutrons inside a model of iron shielding wall. The neutron dose around the surface of the shielding wall was detected less than three orders of magnitude of photons at 10 MV linac. The total neutron dose in a 15 MV linac was about one order higher than that in the 10 MV linac. In addition, the 15 MV linac incident photons clearly generated secondary neutrons inside the iron shielding wall.

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“…The U.S. National Regulatory Commission (NRC) collected and analyzed concrete samples from bio-shield concrete walls during actual decommissioning projects. 53,54 The target radionuclides selected for this analysis were 152, 154, 155 Eu, 60 Co, 54 Mn, 63 Ni, 59 Fe, 160 Tb, 182 Ta, 181 Hf, 51 Cr, 124 Sb, 134 Cs, 85 Sr, 46 Sc, and 65 Zn. Fig.…”

Section: Radioactive Concrete From Decommissioning Of Nuclear Power Pmentioning

confidence: 99%

Editors' Choice—Review—Electro-Kinetic Decontamination of Radioactive Concrete Waste from Nuclear Power Plants

Kim

Choi

Shin

2018

J. Electrochem. Soc.

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Electro-kinetic decontamination has been studied for radioactive concrete of nuclear power plants because of its effective removal of contaminants from deep inside concrete. Although many experiments have been conducted, a systematic comparison has been scarcely conducted. By a thorough review, this study reveals how different conditions of electro-kinetic decontamination changes the decontamination ratio and rate of Cs and Co. The tested conditions include cell configurations (i.e., geometry of concrete waste, electrode materials, and volume of solutions) and operating conditions (i.e., types and concentrations of solutions, electric field, and test duration). The careful analysis suggests the important roles of pH in electrolytic solution, electric field, and pre-treatment. We also discuss the chemical conditions under which the decontamination of Cs and Co was optimized in the presence of an applied voltage. In addition, we critically review the conditions of simulated concrete samples in the previous experiments in comparison with actual nuclear plant data.

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Long-lived activation products in reactor materials

Abstract: N R C FIN 82296 WBTICE PQRTlbNS OF THIS REPORT ARE ILlE64BLE. It has been reproduced from the hest availahle copf to permit the broadest possible avrllability.

Cited by 47 publications

References 1 publication

Sensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure Materials

Sensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure Materials

Estimation of neutron and gamma radiation doses inside the concrete shield wall for 10 and 15 MV medical linear accelerators

Editors' Choice—Review—Electro-Kinetic Decontamination of Radioactive Concrete Waste from Nuclear Power Plants

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