Criticality safety analysis of GBC-32 spent fuel cask with improved neutron absorber concept

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F20%3A43958951" target="_blank" >RIV/49777513:23220/20:43958951 - isvavai.cz</a>

Result on the web

<a href="https://drive.google.com/file/d/10sYvkAuQ3xp6va52e5fyi3qvpS6XqIPk/view" target="_blank" >https://drive.google.com/file/d/10sYvkAuQ3xp6va52e5fyi3qvpS6XqIPk/view</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1051/epjconf/202124717003" target="_blank" >10.1051/epjconf/202124717003</a>

Result language

angličtina

Original language name

Criticality safety analysis of GBC-32 spent fuel cask with improved neutron absorber concept

Original language description

Higher enrichment of nuclear fuel along the manufacturing limit of boron content in steel and aluminum alloys represents a significant challenge in designing spent fuel transport and storage facilities. One possible solution for spent fuel pools and casks is the burnup credit method that allows for decreasing very high safety margins associated with fresh fuel assumption in spent fuel facilities. An alternative solution based on placing neutron absorber material directly into the fuel assembly is proposed here. A neutron absorber permanently fixed in guide tubes decreases system reactivity more efficiently than absorber sheets between the assemblies. The efficiency of the newly proposed concept is demonstrated on the criticality safety analysis of the GBC-32 spent fuel cask. Absorber rods from 8 different elements are placed within Westinghouse OFA 17x17 guide tubes. Currently used boron is a good option because of high absorption cross section, low atomic mass and chemical compatibility with various alloys. Alternative options (e.g., Sm, Eu, Gd, Dy, Hf, Re, Ir) are based on very good absorbers that do not require alloy compatibility since the absorbers can be placed inside zirconium or steel cladding. Because of high efficiency of the newly proposed absorber concept, boron content in BORAL sheets can be decreased to more competitive economics. Moreover, fuel assembly pitch is investigated in order to change cask wall inner diameter that will result in lower material consumption for the cask wall with the same shielding thickness.

Czech name

—

Czech description

—

Type

O - Miscellaneous

CEP classification

—

OECD FORD branch

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Project

<a href="/en/project/TK02010102" target="_blank" >TK02010102: Optimization of Dry Storage for Spent Nuclear Fuel</a><br>

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2020

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů