Mechanistic source terms for the XE-100 reactor XSTERM Code Development Approach - 18587
Creators
- 1. X Energy LLC: 7701 Greenbelt Road, Greenbelt, Maryland 20770 (United States)
Description
X-Energy is developing the Xe-100 pebble bed modular High Temperature Gas Reactor (HTGR) as an advanced nuclear power source. To achieve its safety objectives, the Xe-100 reactor relies on materials inherent characteristics and passive safety features. Key features include the inherent high temperature characteristics of TRISO-coated fuel particles, graphite moderator, and helium coolant, along with passive heat removal capability of a low-power-density core. This paper will describe the approach adopted by X-Energy to develop and validate mechanistic source terms for the Xe-100. The Mechanistic Source Term (MST) approach for the Xe-100 reactor will build upon that of the prior DOE Next Generation Nuclear Program (NGNP) (Refs. 1, 2, 3 and 4). MST development is closely related to Fuel Qualification (FQ), Licensing Basis Event (LBE) selection and Probabilistic Risk Assessment (PRA). This paper provides a brief overview of the MST road map process. Software plays a crucial role in establishing and quantifying MSTs required for licensing the Xe-100. An insight into X-Energy s comprehensive, integrated software development program for calculating time-dependent radionuclide releases from the Xe-100 over a wide range of events is provided. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 14 p.
Conference
- Title
- International Topical Meeting on High Temperature Reactor Technology
- Acronym
- HTR 2016
- Dates
- 6-10 Nov 2016
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52073067
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COATED FUEL PARTICLES; COMPUTER CODES; COOLANTS; GRAPHITE; HEAT; HELIUM; HTGR TYPE REACTORS; NUCLEAR FUELS; POWER DENSITY; PROBABILISTIC ESTIMATION; RADIOISOTOPES; REACTOR LICENSING; REACTOR SAFETY; RISK ASSESSMENT; SOURCE TERMS; TIME DEPENDENCE
- Descriptors DEC
- CALCULATION METHODS; CARBON; ELEMENTS; ENERGY; ENERGY SOURCES; FLUIDS; FUEL PARTICLES; FUELS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; ISOTOPES; LICENSING; MATERIALS; MINERALS; NONMETALS; RARE GASES; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SAFETY
Optional Information
- Notes
- 22 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)