Published 2011 | Version v1
Miscellaneous

Transient analysis of a hydrogen-desalination cogeneration nuclear power plant : accident scenarios within the hydrogen production plant

  • 1. Korea Adv. Inst. of Science and Tech., Dept. of Nuclear and Quantum Engineering, Yuseong-gu, Daejeon (Korea, Republic of)

Description

The WHEN (Water-Hydrogen-Electricity Nuclear gas-cooled reactor) system is an integrated system based on a nuclear power plant coupled with desalination and hydrogen production. The WHEN system integrates the HELP (High-Economical Low-Pressure) IS (Iodine- Sulfur) cycle for hydrogen production and the CD (Capacitive Desalination) + MED (Multi Effect Distillation) Hybrid system for desalination on top of the HTGR (High-Temperature Gas-cooled Reactor), which generates electricity. The WHEN system can enhance energy utilization by as much as 70%, and it can be flexibly designed according to various user needs. When we operate this type of cogeneration nuclear power plant, the load balance of each system is critical for the continuous operation of the entire system. A set of transient scenarios was simulated using a system analysis code (the GAMMA code), which can take into account the flow path design of hydrogen production coupling, i.e., undercooling and overcooling transients that are initiated in the hydrogen production plant. From the results of a safety analysis, we confirmed that the undercooling and overcooling transients initiated in the IS cycle do not lead any serious safety problems on the WHEN system. (author)

Part of:
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-05-6
Imprint Title
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
Imprint Pagination
766 Megabytes
Journal Page Range
[12 p.]

Conference

Title
14. International Topical Meeting on Nuclear Reactor Thermalhydraulics
Acronym
NURETH-14
Dates
25-30 Sep 2011
Place
Toronto, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47071177
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COGENERATION; DESALINATION REACTORS; GAS COOLED REACTORS; HYDROGEN PRODUCTION; NUCLEAR POWER PLANTS; SAFETY ANALYSIS
Descriptors DEC
NUCLEAR FACILITIES; POWER GENERATION; POWER PLANTS; REACTORS; STEAM GENERATION; THERMAL POWER PLANTS

Optional Information

Notes
Paper NURETH14-561, 6 refs., 6 tabs., 16 figs.