ML22181B176

Enclosure 1 - Changes to PSAR Chapter 4.2

ML22181B176
Person / Time
Site:	Hermes File:Kairos Power icon.png
Issue date:	06/30/2022
From:	Kairos Power
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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ML22181B174	List: ML22181B175 ML22181B176
References
KP-NRC-2206-015
Download: ML22181B176 (4)

Text

KP-NRC-2206-015

Enclosure 1 Changes to PSAR Chapter 4.2

(Non-Proprietary)

Preliminary Safety Analysis Report Reactor Description

core. A fuel -free carbon matrix shell is located on the surface of the fuel region to protect the fuel primarily from mechanica l damage.

The fuel annulus is composed of a carbon matrix embedded with TRISO fuel particles with a packing fraction of approximately 37%. The fuel particles are located near the pebble surface which reduces particle temperature s relative to non -annular de signs. The TRISO particles are fabricated in accordance with a fuel specification that is similar to DOE s AGR program fuel particles matching critical parameters related to fuel performance. The kernels are composed of UCO, a mixture of UO 2, UC, and UC 2 phases, which differs from the traditional TRISO fuel particle kernels containing only UO 2. The addition of carbon to the kernel mitigates the generation of CO gas thus reducing the risk of kernel migration, over -

pressurization of the particle with CO gas, and CO gas reactions with the SiC layer. The fuel pebbles are safety -related.

T he reactor also contains mo derator pebbles. These pebbles have the same diameter as the fuel pebbles, contain no uranium, and are made of graphite matrix material. The moderator pebbles have the same buoyancy characteristics as the fuel pebbles. As described in Section 4.5, these pebbles provide neutron moderation. The moderator pebbles are non -safety related.

Typical f F uel properties are provided in Table 4.2 -1 (particle) and Table 4.2 -2 (pebble). The primary safety -related functions performed b y each of the fuel components are described in Table 4.2 -3.

4.2.1.2 Fuel Qualification The qualification of the initial reactor fuel is based on U.S. and international historical experience with TRISO fuel elements and the advancement in fuel technology through the DOE AGR program. This historical experience provides confidence that the reactor will operate with large thermal margins and therefore the integrity of the fuel is not expected to be challen ged. The DOE initiated the AGR project in the early 2000s to design and develop a High Temperature Gas Reactor to support the U.S. domestic electricity and process heat market. A critical part of this effort was evaluating past issues with U.S.

manufacture d particle fuel in comparison to the successful German experience. The result was a TRISO fuel particle design that was fabricated at laboratory and engineering scale s and irradiated in a series of tests in the Advanced Test Reactor at the Idaho National L aboratory (INL). These irradiation tests serve as a foundation for the qualification of a TRISO fuel particle design for application in the KP -FHR test reactor.

The fuel qualification program is described in the Fuel Qualification Methodology for the Kai ros Power Fluoride Salt -Cooled High Temperature Reactor (KP -FHR) topical r eport (Reference 2 ). The main elements of this qualification program are:

• DOE AGR and Legacy Data

• Fuel Specification, Manufacturing, and Quality Control through Inspection

• Fuel Element Phenomena Identification and Ranking Table

• Development of Operating Envelope

• Fuel Element Laboratory Testing

• Fuel Irradiation Test Program

• Fuel Performance Modelling

• Fuel Surveillance Program The AGR test experience provides confidence that TRISO p article failure fractions in particles manufactured to similar specifications in a quality -controlled program will result in similar very low failure fractions.

Kairos Power Hermes Reactor 4 - 4 Revision 0 Preliminary Safety Analysis Report Reactor Description

Table 4.2 -1 : Fuel Particle Properties

Property Nominal Specified Value

Kernel diameter ( µ m) 425

Buffer thickness ( µ m ) 100

PyC thickness ( µ m ) 40

SiC thickness ( µ m ) 35 Kernel density (g/cm 3 ) > 10.4

Buffer density (g/cm 3) 1.05

PyC density (g/cm 3 ) 1.90

SiC density (g/cm 3) > 3.19

C/U atomic ratio 0.40

O/U atomic ratio 1.50

PyC BAF < 1.045

Kairos Power Hermes Reactor 4 -14 Revision 0 Preliminary Safety Analysis Report Reactor Description

Table 4.2 -2 : Fuel Pebble Dimensions and Properties

Property Specified Mean Nominal Value

Fuel Pebble

Outer shell outer radius ( c m) 2.0 Average Pebble Density (g/cm 3) 1.74

TRISO particles packing fraction (%) ~37

Pebble Uranium loading (g) 6.0

Number of particles per pebble ~ 16,000

Moderator Pebble

Moderator Pebble Radius (cm) 2.0 Average Density (g/cm 3) 1.74

Kairos Power Hermes Reactor 4 -15 Revision 0