Tritium transport in the vacuum vessel pressure suppression system for helium cooled pebble bed

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F23%3AN0000040" target="_blank" >RIV/26722445:_____/23:N0000040 - isvavai.cz</a>

Result on the web

<a href="https://www.sciencedirect.com/science/article/pii/S0920379623004520" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0920379623004520</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2023.113870" target="_blank" >10.1016/j.fusengdes.2023.113870</a>

Result language

angličtina

Original language name

Tritium transport in the vacuum vessel pressure suppression system for helium cooled pebble bed

Original language description

In the frame of the safety studies for the EU-DEMO reactor, attention is paid to the hydrogen concentration in the vacuum vessel and connected volumes since it would lead to a possible hazard of releasing tritium and activated dust. The risk of explosion cannot be excluded a priori if H2 stockpiles. For this reason, in both water (WCLL) and helium (HCPB) cooled breeding blanket concepts of EU-DEMO, the problem is under investigation with a crossreference between the available technologies in fission (such as the Passive Autocatalytic Recombiners - PAR) and fusion application. In particular, the recent analyses pointed out the implementation of the PARs into the Vacuum Vessel Pressure Suppression System or linked systems. This paper evaluates the Hydrogen behavior (main mobilized tritium source term) for the Helium-Cooled Pebble Bed (HCPB) VVPSS concept. The analyses preliminary investigate the stratification of the hydrogen mass inventory inside the PSS. In particular, a MELCOR 1.8.6 model of the PSS, based on past activities aimed at dust transport and thermohydraulic analyses, is adopted. The paper also introduces the applicability of PAR technology in the operation range of fusion devices, analyzing the problem of the recombination rate due to the dilution of Hydrogen after a Helium blowdown.

Czech name

—

Czech description

—

Type

J_imp - Article in a specialist periodical, which is included in the Web of Science database

CEP classification

—

OECD FORD branch

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

Project

<a href="/en/project/9D22001" target="_blank" >9D22001: Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium</a><br>

Continuities

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

Publication year

2023

Confidentiality

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

Name of the periodical

Fusion Engineering and Design

ISSN

0920-3796

e-ISSN

1873-7196

Volume of the periodical

194

Issue of the periodical within the volume

September

Country of publishing house

CH - SWITZERLAND

Number of pages

7

Pages from-to

1-7

UT code for WoS article

001040403000001

EID of the result in the Scopus database

2-s2.0-85163589112