Neutron absorber for VVER-1000 storage, transport and final disposal facilities

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F21%3A43963776" target="_blank" >RIV/49777513:23220/21:43963776 - isvavai.cz</a>

Result on the web

<a href="https://www.djs.si/nene2021/proceedings/pdf/NENE2021_1012.pdf" target="_blank" >https://www.djs.si/nene2021/proceedings/pdf/NENE2021_1012.pdf</a>

DOI - Digital Object Identifier

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Result language

angličtina

Original language name

Neutron absorber for VVER-1000 storage, transport and final disposal facilities

Original language description

The recent increasing demand for better nuclear fuel utilization requires higher enriched uranium fuels which is a challenge for spent fuel handling facilities in all countries with nuclear power plants. The operation with higher enriched fuels leads to reduced reserves to legislative and safety limits of spent fuel transport, storage and final disposal facilities. In some cases, the required boron amount in the absorber plates or tubes can be higher than current metallurgy processes allows. This study addresses the neutron absorber solution with significantly increased nuclear safety and improved economics where a concept of inseparable neutron absorber is introduced to achieve fuel reactivity decrease. Storage, transport and disposal facilities for VVER-1000 nuclear fuel can be modified with the neutron absorber for better nuclear safety and better economics. For selected fuel handling facilities (spent fuel pool, storage and transport spent fuel cask, final disposal cask), both approaches are used independently. In the first part of criticality safety analysis, neutron absorber is used without facility changes to show maximum increase of nuclear safety in reactivity decrease. In the second part, neutron absorber is used with facility changes for improved economics while achieving the same level of nuclear safety, i.e. the same neutron multiplication factor. Improved economics include boron amount reductions, steel thickness reduction and increased facility capacity.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

10304 - Nuclear physics

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

2021

Confidentiality

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

Article name in the collection

Proceedings of the International Conference Nuclear Energy for New Europe (NENE 2021)

ISBN

978-961-6207-51-5

ISSN

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e-ISSN

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Number of pages

8

Pages from-to

"1012.1"-"1012.8"

Publisher name

Nuclear Society of Slovenia

Place of publication

Ljubljana

Event location

on-line, Bled, Slovenia

Event date

Sep 6, 2021

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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