Feedback on neutron capture cross-section of <sup>234</sup> U from analysis of measured inventories of UO <sub>2</sub> fuel irradiated in TMI unit 1-Reference-Cited by-同舟云学术

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Feedback on neutron capture cross-section of ²³⁴ U from analysis of measured inventories of UO ₂ fuel irradiated in TMI unit 1

Published:2024-07-12 Issue: Volume: Page:1-8
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Yamamoto Toru¹

Affiliation:

1. Nuclear Engineering Consultant, Yokohama, Japan

Publisher

Informa UK Limited

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2024.2373912

Reference18 articles.

1. JENDL-4.0: A New Library for Nuclear Science and Engineering

2. SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions

3. Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validation

4. Data formats and procedures for the evaluated nuclear data file. ENDF/B-V. National Nuclear Data Center, Brookhaven National Laboratory; 1983. BNL-NCS-50496 (ENDF-102).

5. Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3

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