design and safety approach of htgrs - atoms for peace · pdf filedesign and safety approach of...
TRANSCRIPT
![Page 1: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/1.jpg)
Design and safety approach of HTGRs
Jim C. Kuijper
IAEA Training Course on High-Temperature
Gas-Cooled Reactor Technology
Serpong, Indonesia, 19-23 October 2015
![Page 2: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/2.jpg)
Introduction & outline (1)
Approach ::: Philosophy ::: Background
Context - Basic HT(G)R concepts
Some history
Origin of design criteria o Safety constraints, limits o Application & performance
Specific characteristics of HTGR systems (focus: reactor…) o Reactor physics (neutronics) o Material properties o Thermal hydraulics & heat transfer
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 2
![Page 3: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/3.jpg)
Introduction & outline (2)
HTGR core design characteristics o Core shape and dimensions o Fuel selection and (re-) load strategy
Concluding remarks…
Presentation is based on the chapter “(V)HTR in detail – Design & safety approach” of the JRC-IET book on Generation IV systems (to be published December 2015?)
State-of-the-art ~December 2014
With special thanks to the originators of the illustrations and other info, in particular to Prof.dr.ir. Jan-Leen Kloosterman (Delft University of Technology, NL) and Mr. Xavier Raepsaet (CEA Saclay, France)
For further (detailed/background) information, see the [References]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 3
![Page 4: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/4.jpg)
Context (1)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 4
![Page 5: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/5.jpg)
Context (2)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 5
![Page 6: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/6.jpg)
Context (3)
(Very) High Temperature Gas-Cooled Reactor (Gen III+, IV)
(TRISO) coated particle fuel (He) gas-cooled Graphite moderator/reflector Epi-/thermal spectrum Pebble-bed and prismatic Influence of design choices on behaviour Some details of (V)HT(G)R (reactor) physics & thermal hydraulics HGTR fuel cycle – flexibility (other presentation) Not about: Calculation/analysis methods (other presentations)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 6
![Page 7: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/7.jpg)
Basic HTGR concepts
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 7
![Page 8: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/8.jpg)
Pebble-bed fuel
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 8
(J.L. Kloosterman, RAPHAEL Eurocourse, March 2007)
![Page 9: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/9.jpg)
“Prismatic” fuel
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 9
(W. Bernnat, RAPHAEL Eurocourse, March 2007)
![Page 10: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/10.jpg)
Some history
Early gas-cooled reactors
HT(G)R plants constructed and operated
Former HGTR designs
“Current”HTGR designs
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 10
![Page 11: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/11.jpg)
Early gas-cooled reactors Name or acronym Oak Ridge Graphite
Reactor Windscale piles P2 Magnox AGR Tokai-1
Magnox
Location Oak Ridge, TN USA
Sellafield UK
Saclay France
UK UK Tokai Japan
Operation years 1943 - 1963 1950 1951 1956 - present 1962 - present
1966 - 1998
Fuel U metal cyl. Al cladding
Nat. U Nat. U metal Al cladding
Nat. U Nat. U Nat. U
Moderator Graphite Graphite Heavy water Graphite Graphite Graphite
Coolant Air air N2 (initially) CO2 (later)
CO2 CO2 CO2
Power [MWth/MWe]
1 – 4/- - 2 / - - / 166 - / 166
Reference [R.1.7] [R.1.8] [R.1.9]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 11
![Page 12: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/12.jpg)
HTGR plants constructed & operated Name/ Acronym
DRAGON Peach Bottom
Fort St. Vrain
AVR THTR HTTR HTR-10
Location UK USA USA Germany Germany Japan China
Operation Years
1964 – 1975
1966 - 1974
1976 – 1989
1967 - 1988
1985 - 1991 1999 - present
2000 – present
Fuel element Cylinder Cylinder Cylinder in hex. block
Sphere Sphere Cylinder in hex. block
Sphere
Fuel coating TRISO BISO TRISO BISO BISO TRISO TRISO
Fuel kernel Carbide Carbide Carbide Oxide Oxide Oxide Oxide
Enrichment [%] 90 93 17
Power [MWth/MWe]
20 / - 115 / 40 842 / 330 46 / 15 750 / 300 30 / - 10 / -
Tin / Tout [oC] 350 / 750 377 / 750 400 / 775 270 / 950 270 / 750 395 / 950 300 / 700
He pressure [bar]
20 25 49 11 40 40 30
Power density [W/m3]
14 8.3 6.3 2.6 6.0 2.5 2.0
Reference [R.3.4] [R.3.4] [R.3.4] [R.3.4] [R.3.4] [R.3.4] [R.3.4]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 12
![Page 13: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/13.jpg)
HTGR designs – Some basic data
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 13
[H. Nickel, HTR/ECS, 2002]
![Page 14: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/14.jpg)
Former HTGR designs …
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 14
[W. von Lensa, HTR/ECS, 2002]
![Page 15: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/15.jpg)
USA – From prototype to commercial design
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 15
[W. von Lensa, HTR/ECS, 2002]
![Page 16: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/16.jpg)
“Current” designs Name/ Acronym
MHTGR GT-MHR HTR-Modul PBMR HTR-PM
Location USA USA/Russia Germany South Africa China
Fuel element Compact in hex. block
Compact in hex. block
Sphere Sphere Sphere
Fuel coating TRISO TRISO TRISO TRISO TRISO
Fuel kernel UCO/Th-oxide UCO/MOX Oxide Oxide Oxide
Enrichment [%] 20 19.8 7.8 4.2 – 9.6 8.5
Power [MWth/MWe]
4x350/508 600 200 400/165 2 x 250/211
Tin / Tout [oC] 259 / 687 491 / 850 250 / 700 500 / 900 250 / 750
He pressure [bar]
63.7 70.7 60 90 70
Power density [MW/m3]
5.9 6.6 3.0 4.8 3.2
Remarks Preliminary design completed / Licensing process not finalised
Licensed Project terminated in 2009
Under construction
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 16
![Page 17: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/17.jpg)
Observations
Great variety in parameters (dimensions, power, He pressure, etc.)
Trend towards higher coolant outlet temperature (HTGR VHTR)
High degree of “passive safety” possible (if sufficiently low power density…)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 17
![Page 18: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/18.jpg)
Origin of design criteria
INPRO (IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles) [R.2.1]
Safety Constraints / limitations
Application & performance
Design...
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 18
![Page 19: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/19.jpg)
INPRO (1)
Comprehensive methodology for the assessment of safety and performance of an innovative reactor (so the HTGR/VHTR)
INPRO Volumes 1-9 [R.2.1]: 1. Overview of the methodology
2. Economics
3. Infrastructure
4. Waste management
5. Proliferation resistance
6. Physical protection
7. Environment
8. Safety of nuclear reactors
9. Safety of nuclear fuel cycle facilities
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 19
![Page 20: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/20.jpg)
INPRO (2)
Evaluation of innovative nuclear system designs: o Basic Principles
o User Requirements (safety, performance, ...)
o Criteria (= Indicator + Acceptance Limit)
Only a (very) small subset hereof in this presentation...
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 20
![Page 21: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/21.jpg)
Safety (1)
Many ways to define nuclear safety (IAEA, USNRC, ... [R.2.2])
INPRO volume 8 (reactors) and volume 9 (fuel cycle facilities)
Practical definition:
A nuclear reactor (system) is classified as “safe” if there is no health hazard to the public or personnel under all conceivable normal (operation, anticipated deviations) and off-normal (DBA, BDBA) sitiations.
Include “almost inconceivable” situations (“stress test”)???
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 21
![Page 22: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/22.jpg)
Safety (2)
This implies:
No need for off-site evacuation or taking shelter near the site boundary
No need for moving mechanical components to ensure this
Exposure to personnel significantly lower than current internationally accepted values
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 22
![Page 23: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/23.jpg)
Safety (3)
Safety design philosophy for a nuclear reactor: criteria at 3 distinct levels:
Top level criteria: o National regulatory body International/IAEA standards
o ALARA [R.2.3]
Basic safety functions: o Control of reactivity/criticality (ensure subcriticality)
o Removal of (decay) heat from (the fuel in) the core (temperature limit)
o Confinement of radioactive material
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 23
![Page 24: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/24.jpg)
Safety (4)
Defence-in-depth principle to prevent, mitigate and control any off-normal event. The IAEA formulation distinguishes 5 levels of defence: o Prevent deviations from normal operation
o Detect and control deviations
o Prevent core damage by incorporating safety features/systems
o Mitigate consequences (on-site and off-site)
o Mitigate radiological consequence (on-site and off-site)
Prevention and mitigation systems.
To be applied to all safety-related activities (organisational/behavioural/design) and all (reactor) system states (full power/low power/various shutdown states).
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 24
![Page 25: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/25.jpg)
Safety (5)
Alternative formulation of Defense-in-depth (USNRC [R.2.4][R.2.4a]):
“…, the philosophy ensures that safety will not be wholly dependent on any single element of the design, construction, maintenance, or operation of a nuclear facility”.
Both formulations share the notion of multiple, independent layers of defence or multiple barriers of protection against health hazard to public and personnel.
HTGR/VHTR can incorporate these barriers in a passive manner.
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 25
![Page 26: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/26.jpg)
Application & performance
Envisaged application & required performance (technical/economic), mostly connected to the possibility of high coolant outlet temperature:
Electricity and (process) heat
High fuel temperature basic design choices: o Refractory materials in the core: graphite o Use of (inert) gas as coolant: He, CO2, H2
o Coated particle ful (SiC, PyC)
Other requirements, e.g. high degree of sustainability:
In GIF usually attribited to fast spectrum systems (“closing the fuel cycle”) [R.2.5]
HTGR/VHTR may also provide a high degree of sustainability [R.2.6][R.2.6a][R.2.7]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 26
![Page 27: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/27.jpg)
Design (1)
Several definitions of “design” possible... (see e.g. http://www.oxforddictionaries.com)
For a reactor system like a HTGR, “design” refers to the choice of materials, dimensions, and arrangement of structures and components and the choice of relevant (design) parameters (e.g. nominal power level, temperature, pressure, but also dimensions and dimensional changes) during normal operation and off-normal states.
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 27
![Page 28: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/28.jpg)
Design (2)
Application to structures and components at different levels:
Reactor system and structures’ dimensions, components and materials more or less fixed
Fuel elements (materials and dimensions) some details may change during the lifetime of the reactor
Core layout and loading scheme variation from cycle to cycle (or continuous...)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 28
![Page 29: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/29.jpg)
Origin of design criteria – overview
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 29
Application – Performance, e.g.:
Electricity production
CHP
District heating
H2-production (process heat in general) [R.3.3]
Pu/MA utilization/incineration [R.2.6][R.2.6.a][R.2.7]
Fuel utilisation – Waste production (sustainability), e.g.:
High burn-up
High conversion ratio
Reduction of Pu and/or MA [R.2.6][R.2.6a]
Minimise production of waste
Direct disposal
Operation, e.g.:
Cycle length
Maintenance
Direct/indirect cycle
Plant life
Multiple modules
Safety – inherently safe design (?)
Normal operation – Incidents/Accidents
Excess reactivity
Control rod worth – Shutdown margin
Xe-effect / Xe-oscillations
(Negative) temperature reactivity coefficient
Max. (fuel) temperature
Max. power per fuel element (particle, pebble, compact)
Fast fluence in fuel and core internals
Max. burn-up
Decay heat removal (passive)
???
Constraints (limits)
Reactor physics/neutronics
Thermal hydraulics
Material science
???
Design criterion ≈ Range of permissible parameter values
![Page 30: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/30.jpg)
Specific characteristics of HTGR
Characteristics and associated constraints/limits:
Reactor physics/neutronics: mutual interaction of the materials in the reactor with the neutron field
Material properties
Thermal hydraulics and heat transfer
...
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 30
![Page 31: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/31.jpg)
Reactor physics/neutronics (1)
Neutronic properties of HTGR materials – which materials?
Interaction of materials with neutron field: o several reactions (fission, capture, scatter, (n,2n), (n,3n),…) possible per
nuclide o σ(E), η(E),... o material compositions/distribution changing with time
Radioactive decay
Moderator-to-fuel ratio (M/F ≈ C/U) => k
Material (nuclide) distribution over space → o Neutron distribution over energy (spectrum) o Neutron distribution over space => power distribution => temperature
distribution, decay heat distribution
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 31
![Page 32: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/32.jpg)
Reactor physics/neutronics (2)
Enrichment ε, burn-up, conversion ratio, control rod worth,…
Resonance self-shielding – Doppler effect – CP dimensions
Neutron leakage o H/D ratio (cylindrical core)
o Neutron streaming
o Minimum neutron leakage for cylindrical core: H/D ≈ 0.924
keff ≥ 1 (uncontrolled...)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 32
![Page 33: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/33.jpg)
Materials in HTGR
Fissile: U235, U233, Pu239, Pu241 (usually oxide or (oxy-) carbide)
Fertile: U238, Th232 (usually oxide)
Moderator: graphite (C12)
Other materials in the fuel (e.g. inert matrix material)
Structural material: graphite, SiC
Control elements: steel, B4C
Fission products: Xe135, Sm149, Mo95, Cs133, Cs135, Tc99, Ag110, Nd145, Xe131, Rh103, Pm147, Eu153,…
Heavy isotopes: Pa233, U234, U236, Np239, Pu240, Pu242, Am…, Cm…, …
Coolant: He (“neutronically inert”)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 33
![Page 34: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/34.jpg)
Neutron flux spectral distribution (1) Higher thermal and epithermal flux than in LWR
Dependent upon HM load, enrichment and burn-up
(W. Scherer, HTR/ECS, 2002)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 34
![Page 35: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/35.jpg)
Neutron flux spectral distribution (2)
Dependent upon HM load, enrichment and burn-up [R.1.6]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 35
![Page 36: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/36.jpg)
Neutron flux spectral distribution (3)
Dependent upon HM load, enrichment and burn-up [R.1.6]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 36
![Page 37: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/37.jpg)
Controllability
Position of control structures (elements, absorber spheres,[R.1.5]) must be such that: o Sufficient subcriticality can be ensured at all times, even if the most reactive
element can not be inserted (“shutdown margin”).
o Sufficient margin for altering the reactivity (“control rod worth”) to counter changes in reactivity during operation
No real problem for prismatic block type HTGR
Limit on radial dimensions of core cavity for cylindrical pebble bed HTGR (on the other hand: THTR...)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 37
![Page 38: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/38.jpg)
He coolant
Helium (mostly He4) is transparent to neutrons: ”No” change in reactivity from change in He temparature or density
DLOFC is almost purely thermal-hydraulic issue
No (positive) void coefficient No limits on the use of Pu fuel
Functions of coolant (He) and moderator (graphite, C12) not combined: No correlation between cooling geometry and M/F-ratio High degree of flexibility w.r.t. fuel management while retaining excellent safety characteristics
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 38
![Page 39: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/39.jpg)
M/F – Moderator-to-fuel ratio
M/F ≈ C/U (or C/HM or “light atoms”/HM)
Range: 500 to 3000
Under moderated?
[R.1.6]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 39
![Page 40: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/40.jpg)
Coated particle size
Fuel in kernel of TRISO (or BISO) particle
Resonance self-shielding (hence resonance escape probability) depends on kernel and CP size
Double heterogeneity
[R.1.6]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 40
![Page 41: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/41.jpg)
Coated particle size (2)
Harder spectrum and higher conversion for smaller particles
For smaller particles curve tend to the one for the homogeneous case
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 41
![Page 42: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/42.jpg)
Migration length – Prompt fission chain
“Neutronic” dimensions of the core: Compare actual dimensions with characteristic distances of neutronics (migration length, prompt fission chain length) o Migration length M o Prompt fission chain length:
(J. Keijzer, PhD thesis, Delft, 1996 [R.3.1a])
Prismatic type: M ~ 22 cm; lPFC = 668 cm
Pebble-bed type: M ~ 32 cm; lPFC = 972 cm
If characteristic dimension of the core > prompt fission chain length, axial Xe-oscillations may occur
Core height H limited to approx. 10 m
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 42
2
PFC
M6l
![Page 43: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/43.jpg)
Axial Xe-oscillations (1)
Xe-effect
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 43
![Page 44: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/44.jpg)
Axial Xe-oscillations (2)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 44
![Page 45: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/45.jpg)
Temperature influence on reactivity
Mainly 3 temperature coefficients of reactivity:
W.r.t. temperature of the fuel (CP) (Doppler effect)
W.r.t. temperature of the moderator (in the core)
W.r.t. temperature of the reflector
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 45
![Page 46: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/46.jpg)
Doppler effect vs. burn up
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 46
![Page 47: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/47.jpg)
Graphite temperature effect
Moderator and reflector
Shift of Maxwellian peak to higher energy if temperature increases
Lower effective cross section (reaction rate) for “1/v” cross sections (thermal neutron energies)
Possibly higher effective cross section (reaction rate) for “non 1/v” or resonance cross sections (intermediate neutron energies)
Net effect may be positive or negative, depending on (local) circumstances (difference between reflector and moderator)
Example: equilibrium state (time-independent nuclide distribution)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 47
![Page 48: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/48.jpg)
Temperature coefficients of reactivity (1)
PBMR-400 in equilibrium state (U-based fuel)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 48
![Page 49: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/49.jpg)
Temperature coefficients of reactivity (2)
PBMR-400 in equilibrium state (Pu-based fuel)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 49
![Page 50: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/50.jpg)
Material properties
Radiation damage o Fuel (coatings) o In-core structures (e.g. reflector) o Fast fluence (E > 0.1 MeV)
(Chemical) compatibility of coolant and other materials – not a big problem for He
Thermal stress & Chemical interactions with(in) CPs o Limit retention capability of FP and actinides o Max. acceptable release (R/B ratios) limit on burn-up
Limit on coated particle temperature (1600 oC/1250 oC)
Limits on material temperatures in general → limit on coolant output temperature
Wigner effect in graphite → minimum coolant entrance temperature of 200 oC
Many (other) material properties of materials used in HTGR components, with influence on performance and safety. Should be properly addressed in the design process
See e.g. [R.3.3] and [R.3.4] for applicable codes and standards
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 50
![Page 51: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/51.jpg)
Fuel at very high burn up
U-based fuel: 150 MWd/kg
Pu-based fuel: > 700 MWd/kg achieved in Dragon and Peach Bottom unit 1:
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 51
![Page 52: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/52.jpg)
Dimensional changes in graphite
30 years of irradiation at fast flux of 3x1013 cm-2s-1 (above 0.1 MeV) gives fast fluence of 2.5x1022 cm-2
Dimensional (and other) changes in graphite by radiation damage [R.1.5]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 52
![Page 53: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/53.jpg)
Failure of coated particles – Fast fluence
Fast fluence < 5x1021 cm-2 (TRISO) (less restrictive nowadays?)
For CP failure mechanisms, see [R.3.1][R.3.5][[R.3.6][R.2.9]
[R.1.5]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 53
![Page 54: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/54.jpg)
Failure of coated particles – Temperature (1)
> 1250 oC fission product attach on SiC layer
> 1600 oC decomposition effects and porosity in SiC layer
> 2000 oC thermal decomposition of SiC dominant mechanism
See [R.3.1][R.2.9]
Maximum design base event fuel temperature: 1600 oC
Maximum (peak) fuel temperature during normal operation: 1250 oC
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 54
![Page 55: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/55.jpg)
Failure of coated particles – Temperature (2)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 55
[R.3.7]
![Page 56: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/56.jpg)
Thermal hydraulics
Transfer heat from fuel to a useful purpose (Tout?)
Heat conduction, convection and radiation [R.3.15]
Coolant properties (thermodynamic, fluid dynamic): He (other possibilities: CO2/H2)[R.1.4]
Cooling geometry o Pebble bed: fixed coolant volume fraction (CVF) o Prismatic block with coolant channels: CVF somewhat more flexible in the design phase
Coolant flow o Mass flow o Flow direction (upward/downward through the core) o Core pressure drop (← core dimensions, friction,…) o ∆p ~ H3
Passive (decay) heat removal capabilities (see [R.3.9][R.3.10][R.3.11][R.3.12][R.3.13] for background info on decay heat) o Core geometry and dimensions, H/D-ratio, friction, … o Free convection
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 56
![Page 57: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/57.jpg)
Pressure drop over the core
Pressure loss Δp over a pebble-bed core as function of core height (He-pressure is 40 bar) [R.1.5]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 57
![Page 58: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/58.jpg)
Coolant volume fraction in core
CVF in pebble bed is more or less fixed (~0.39)
Larger range of possible CVFs in prismatic type (coolant channels in blocks), also < 0.39 → higher fuel density possible → higher power density possible
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 58
![Page 59: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/59.jpg)
Fluctuation of packing density (1)
Fluctuation of packing density has no significant influence on flux distribution or keff [R.3.17][R.3.18][R.3.19]
Stochastic nature of pebble bed has considerable influence on power- and temperature distribution [R.3.17][R.3.18][R.3.19]
Should be taken into account in the design extra margings for critical design parameters
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 59
![Page 60: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/60.jpg)
Fluctuation of packing density (2)
Axial packing fraction profile: measurement and simulation [R.3.17]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 60
![Page 61: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/61.jpg)
HTGR core design characteristics
Core shape/dimensions and control structure positions – More or less fixed when design has been fixed
Fuel design and core (re-) loading, possibly including burnable poison – More or less flexible, even for a reactor already in operation.
Detailed design is a complex activity entailing many (other, even important) aspects well beyond this presentation, e.g. issues connected to the production, activation, transport, deposition and resuspension of (graphite) dust, especially in the case of pebble-bed HTGRs [R.4.3].
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 61
![Page 62: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/62.jpg)
Core shape and dimensions
Pebble-bed or prismatic – Coolant Volume Fraction
Cylindrical or annular core
Dimensions o Limits on core height H:
Xe-effect (oscillations) Coolant pressure drop over core ∆p ~ pumping power ~ H3
pumping power < ~5 % of electrical output ∆p < ~ 0.8 bar
o Limits on core diameter D: Control rod worth → annular core (control elements in central column) Passive heat removal → distance to core surface not too large
H/D-ratio o Minimum neutron leakage: H/D ≈ 0.9
Fixed or dynamic inner column
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 62
![Page 63: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/63.jpg)
Control rods – pebble bed
Control rods (usually) in reflector
Worth dependent upon thermal flux, hence reflector graphite temperature
Control rods in pebble bed not impossible (THTR), but not necessary
Reactivity requirements (feasible if cylindrical core radius not too large) o Control and hot shut down: ~4%
o Cold shut down: ~10%
(W. Scherer, HTR/ECS, 2002)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 63
![Page 64: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/64.jpg)
Fuel selection and (re-) load strategy
HTGRs are very flexible with regard to fuel and fuel cycle o Uncoupling between and parameters characterising cooling geometry and
neutronics optimisation
o Solid moderator (no void effect)
Many types of fuel possible in principle – not all fuel designs have been qualified
High burn-up feasible – demonstrated (AVR, Peach Bottom, FSV, THTR)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 64
![Page 65: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/65.jpg)
Physical reasons for flexibility w.r.t. fuel (cycle)
[R.1.6]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 65
![Page 66: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/66.jpg)
Fissile and fertile materials
LEU cycle (enrichment 5 to 19%)
MOX cycle
Pu only
Th (HEU; MEU; Pu) [R.1.6]
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 66
![Page 67: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/67.jpg)
(Re-)load schemes
Pebble bed o MEDUL - continuous re-load o OTTO - Once Through Then Out N.B. Low excess reactivity for MEDUL/OTTO without BP o Peu-à-peu o cartridge o (spatial distribution of) burnable poison o ???
Prismatic o specific re-load scheme (axial and radial shift) o spatial distribution of fuel loading/enrichment o (spatial distribution of) burnable poison o ???
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 67
![Page 68: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/68.jpg)
Examples of reload schemes
OTTO vs. Medul (re-) loading scheme for pebble-bed HTGR
Comparison of radial loading patterns in “HTR-PM” (earlier 380 MW design with 2 m core radius)
Pebble-bed cartridge core with burnable poison (ACACIA)
Two-batch axially shifted re-fueling in GTHTR 300
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 68
![Page 69: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/69.jpg)
OTTO vs. MEDUL (re-) loading scheme
Comparison of axial power density distribution of pebble bed MEDUL (“Mehrfachdurchlauf”) and OTTO (“Einwegbeschickung”) [R.1.5]
Top Bottom
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 69
![Page 70: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/70.jpg)
Comparison of radial loading patterns in “HTR-PM”
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 70
N.B. Earlier version with 2 m core radius and 380 MW thermal power
![Page 71: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/71.jpg)
Radial power distribution “HTR-PM” (380 MW)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 71
![Page 72: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/72.jpg)
Radial power distribution “HTR-PM” (1515oC)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 72
![Page 73: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/73.jpg)
Pebble-bed cartridge core (ACACIA)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 73
![Page 74: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/74.jpg)
ACACIA reactor with annular core (and BP)
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 74
![Page 75: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/75.jpg)
ACACIA – Initially homogeneous BP
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 75
![Page 76: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/76.jpg)
ACACIA – Initially inhomogeneous BP
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 76
![Page 77: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/77.jpg)
Two-batch axially shifted re-fueling in GTHTR 300
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 77
![Page 78: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/78.jpg)
GTHTR 300 core lay-out
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 78
![Page 79: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/79.jpg)
GTHTR 300 fuel layers and re-fueling scheme
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 79
![Page 80: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/80.jpg)
Axial power distribution in GTHTR 300
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 80
![Page 81: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/81.jpg)
Transient behaviour of GTHTR 300
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 81
![Page 82: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/82.jpg)
Concluding remarks
An overview was given on main considerations regarding design– and safety philosophy of present-day HTGR designs
Focus on main features and issues w.r.t. the reactor. Many (even important) issues have NOT been treated in this presentation
Once more it has been shown that HTGR core design is extremely flexible, although there ARE limits
Many different applications, fuels, fuel cycles, etc. possible within constraints of safe operation
Burnable poison can be used to limit excess reactivity while retaining core life
Developments are ongoing, e.g.: o Radial cooling [R.5.1] o “Wallpaper” fuel [R.5.2]
Development towards higher core outlet temperatures (> 1000 oC) is possible [R.2.9] Gen IV VHTR
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 82
![Page 83: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/83.jpg)
Coordinates
Dr.ir. J.C. Kuijper (Jim)
Nuclear Reactor Physics Expert
M +31 6 4022 9728
http://www.nuclic.eu (per 1 January 2016)
Associated with Nuclear-21.Net
http://www.nuclear-21.net
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 83
![Page 84: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/84.jpg)
Terima kasih
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 84
![Page 85: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/85.jpg)
References (1)
[R.1.1] Generation IV International Forum, “Technology Roadmap Update for Generation IV Nuclear Energy Systems”, January 2014.
[R.1.2] Generation IV International Forum, “Annual Report 2013”.
[R.1.3] “The Very High Temperature Reactor: A Technical Summary”, Rev. 0, June 2004, MPR Associates Inc.
[R.1.4] C.W. Forsberg, P.F. Peterson, P.S. Pickard, “Molten-salt-Cooled Advanced High-Temperature Reactor for Production of Hydrogen and Electricity”, Nuclear Technology, Vol. 144, No. 3, Pages 289 302, December 2003.
[R.1.5] K. Kugeler & R. Schulten, “Hochtemperatur-reaktortechnik”, Springer-Verlag 1989, ISBN 3-540-51535-6.
[R.1.6] RAPHAEL Eurocourse on V/HTR Technology, IKE, Stuttgart, Germany, 27-29 March 2007, see
ftp://ftp.cordis.europa.eu/pub/fp6-euratom/docs/raphael-eurocourse-seminar-folder-mar-2007_en.pdf, containing:
J.C. Kuijper, “HTGR core design criteria “;
X. Raepsaet, “Physics of the High Temperature Gas-Cooled Reactor Core “.
[R.1.6a] J.L. Kloosterman, “Design criteria for the HTR core”, Lecture, Delft University of Technology, Delft, The Netherlands, 20 November 2008.
[R.1.7] M.W. Rosenthal, “An Account of Oak Ridge national Laboratory’s Thirteen Nuclear Reactors”, ORNL/TM-2009/181, Oak Ridge National Laboratory, Oak Ridge, TN, USA, March 2010.
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 85
![Page 86: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/86.jpg)
References (2) [R.1.8] S.E. Jensen, E. Nonbøl, “Description of the Magnox Type of Gas Cooled Reactor (MAGNOX)”, Risø National Laboratory, Roskilde, Denmark, 1999, ISBN 87-7893-050-2.
[R.1.9] E. Nonbøl, ”Description of the Advanced Gas Cooled Type of Reactor (AGR)”, Risø National Laboratory, Roskilde, Denmark, November 1996, ISBN 87-550-2264-2.
[R.1.10] Fütterer, M.A., et al., “Status of the very high temperature reactor system”, Progress in Nuclear Energy (2014), http://dx.doi.org/10.1016/j.pnucene.2014.01.013
.
[R.2.1] “Guidance for the Application of an Assessment Methodology for Innovative Nuclear Energy Systems, INPRO Manual”, IAEA- TECDOC-1575 Rev. 1, November 2008.
Volume 1 - Overview of the Methodology
Volume 2 - Economics
Volume 3 - Infrastructure
Volume 4 Waste Management
Volume 5 Proliferation Resistance
Volume 6 Physical protection
Volume 7 Environment
Volume 8 Safety of Nuclear Reactors
Volume 9 Safety of Nuclear Fuel Cycle Facilities
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 86
![Page 87: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/87.jpg)
References (3) [R.2.2] N. Prasad Kadambi, “Defence in depth in nuclear safety”, Nuclear Engineering International, 30 January 2013.
[R.2.3] IAEA, "Safety of Nuclear Power Plants: Design", Revision DS-414 to IAEA NS-R-1.
[R.2.4] USNRC, "White Paper on Risk-Informed and Performance-Based Regulation," Staff Requirements Memorandum Regarding SECY-98- 144, March 1, 1999.
[R.2.4a] USNRC, "Strategic Plan: Fiscal Years 2008-2013 (Updated)", NUREG-1614, Vol. 5, February 2012.
[R.2.5] Generation IV International Forum, “Proceedings GIF symposium, Paris, France, 9-10 September 2009”, ISBN 978-92-64-99115-6. Available at: https://inis.iaea.org/search.
[R.2.6] J.C. Kuijper et al., “Plutonium and Minor Actinide Management in Thermal High-Temperature Gas-Cooled Reactors – Publishable Final Activity Report”, Report PUMA-1006-D411g, Euratom 6th Framework Program contract no. FP6-036457, November 2010. Available at: https://inis.iaea.org/search.
[R.2.6a] J.C. Kuijper et al., “Pu and MA management in Thermal HTRs, Quo Vadis – Insights from the Euratom PUMA project”, Paper presented at the IAEA Technical Meeting “Deep Burn HTR”, IAEA, Vienna, Austria, 5-8 August 2013. Available at: http://inis.iaea.org/search. Corresponding paper to be published.
[R.2.7] F. Venneri et al., “The Deep Burn project: 2010 overview and progress“, in: “Actinide and Fission Product Partitioning and Transmutation - Eleventh Information Exchange Meeting”, San Francisco, CA, USA, 1 – 4 November 2010, OECD/NEA Nuclear Science and Nuclear Development 2012, ISBN 978-92-64-99174-3.
[R.2.8] “Uranium 2011, 2012. Resources, Production and Demand. A Joint Report by the OECD Nuclear Energy Agency and the International Atomic Energy Agency”, OECD, Paris, France.
[R.2.9] K. Verfondern, H. Nabielek, J.M. Kendall, “Coated particle fuel for high temperature gas cooled reactors”, Nuclear Engineering and Technology, Vol. 39, No. 5, October 2007.
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 87
![Page 88: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/88.jpg)
References (4)
[R.2.10] S. Knol et al., “The ARCHER Project”, Proc. 7th International Topical Meeting on High Temperature Reactor Technology HTR 2014, INET, Tsinghua University, Beijing, China.
[R.3.1] R.N. Morris, D.A. Petti, D.A. Powers, B.E. Boyack, “TRISO-Coated Particle Fuel Phenomenon Identification and Ranking Tables (PIRTs) for Fission Product Transport Due to manufacturing, Operations and Accidents – Main Report”, Report NUREG-6844 Volume 1, US NRC, July 2004.
[R.3.1a] J. Keijzer, “Investigations of spatial effects in nuclear reactor kinetics “, PhD thesis, Delft University of Technology, Delft, The Netherlands, 5 April 1996.
[R.3.2] A. Meier, W. Bernnat, K. Hossain, G. Lohnert, “Analyses of high temperature pebble bed reactors with plutonium fuel”, Proc. International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009), Saratoga Springs, New York, May 3-7, 2009.
[R.3.3] D. Buckthorpe, J.-S. Genot, “RAPHAEL: Synthesis of achievements on materials and components and future direction”, Proc. 5th International Topical Meeting on High Temperature Reactor Technology (HTR 2010), Nuclear Engineering and Design, Vol. 251, Pages 330 – 343, October 2012.
[R.3.4] B.K. McDowell, M.R. Mitchell, R. Pugh, J.R. Nickolaus, G.L. Schweringen, “High Temperature Gas Reactors: Assessment of Applicable Codes and Standards”, Report PNNL-20869, Prepared for the US NRC, Pacific Northwest National Laboratory, October 2011.
[R.3.5] B. Boer, A.M. Ougouag, J.L. Kloosterman. G.K. Mills, “Stress analysis of coated particle fuel in graphite of high-temperature reactors”, Nuclear Technology, Vol. 162, June 2008.
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 88
![Page 89: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/89.jpg)
References (5) [R.3.6] J. Jonnet, J.L. Kloosterman, B. Boer, “Performance of TRISO particles fuelled with Plutonium and Minor Actinides in a PBMR-400 core design”, Nuclear Engineering and Design, Vol. 240, Pages 1320 – 1331, 2010.
[R.3.7] M.P. LaBar, A.S. Shenoy, W.A. Simon, E.M. Campbell, Y. Hassan, “Nuclear Energy Materials and Reactors Volume II The Gas- Turbine Modular Helium Reactor”, Encyclopaedia of Life Support Systems (EOLSS).
[R.3.8] J.J. Duderstadt & L.J. Hamilton, “Nuclear reactor analysis”, John Wiley & Sons, New York, ISBN 0 471 22363 8, 1976.
[R.3.9] “Decay heat power in light water reactors”, Standard ANSI/ANS-5.1-1994, American Nuclear Society, USA, 1993.
[R.3.10] “Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors (Berechnung der Zerfallsleistung der Kernbrennstoffe von Leichtwasserreaktoren - Teil 1: Uranoxid-Kernbrennstoff für Druckwasserreaktoren)”, Standard DIN 25463-1:2014-02.
[R.3.11] “Calculation of the decay power in nuclear fuels of light water reactors - Part 2: Mixed-uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors (Berechnung der Zerfallsleistung der Kernbrennstoffe von Leichtwasserreaktoren - Teil 2: Uran- Plutonium-Mischoxid (MOX)-Kernbrennstoff für Druckwasserreaktoren)”, Standard DIN 25463-2:2014-02.
[R.3.12] ”Decay heat power in nuclear fuels of high-temperature reactors with spherical fuel elements (Berechnung der Nachzerfallsleistung der Kernbrennstoffe von Hochtemperaturreaktoren mit kugelförmigen Brennelementen)”, Standard DIN 25485-1:1990-05.
[R.3.13] K. Tasaka et al., “Recommendations on Decay Heat Power in Nuclear Reactors”, Journal of Nuclear Science and Technology, Vol. 28, Issue 12, 1991.
[R.3.14] R.B. Bird, W.E. Stewart, E.N. Lightfoot, “Transport Phenomena”, John Wiley & Sons, 3rd printing, February 1963.
[R.3.15] “Heat Transport and Afterheat Removal for Gas Cooled Reactors Under Accident Conditions”, Technical Report IAEA-TECDOC-1163, IAEA, Vienna, Austria, 2000.
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 89
![Page 90: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/90.jpg)
References (6) [R.3.16] G. Melese, R. Katz, “Thermal and Flow Design of Helium-cooled Reactors”, ISBN 0894480278, 1984.
[R.3.17] G.J. Auwerda, ”Core Physics of Pebble Bed High Temperature Nuclear Reactors”, PhD thesis, Delft University of Technology, Delft, The Netherlands, ISBN 978-94-6295-047-4, 22 December 2014.
[R.3.18] G.J. Auwerda et al., “Effects of random pebble distribution on the multiplication factor in HTR pebble bed reactors”. Annals of Nuclear Energy, Vol. 37, 1056, 2010.
[R.3.19] G.J. Auwerda et al., “Effect of non-uniform porosity distribution on thermal hydraulics in a pebble bed reactor”, Proc. NURETH-14, Toronto, Ontario, Canada, 2011.
[R.4.1] P. W. Humrickhouse, “HTGR Dust Safety Issues and Needs for Research and Development”, Report INL/EXT-11-21097, Idaho National Laboratory, Idaho Falls, Idaho 83415, USA, June 2011.
[R.4.2] M. Ragheb, “Nuclear, plasma and radiation science – Inventing the Future”, Web text, Lecture notes Nuclear Power Engineering NPRE 402, University of Illinois at Urbana-Champaign, USA, Spring 2015.
[R.4.3] B.M. Tyobeka, “ADVANCED MULTI-DIMENSIONAL DETERMINISTIC TRANSPORT COMPUTATIONAL CAPABILITY FOR SAFETY ANALYSIS OF PEBBLE-BED REACTORS”, PhD thesis, The Pennsylvania State University, The Graduate School, Department of Mechanical and Nuclear Engineering, August 2007.
[R.4.4] “PBMR COUPLED NEUTRONICS/THERMAL-HYDRAULICS TRANSIENT BENCHMARK - THE PBMR-400 CORE DESIGN - VOLUME 1: THE BENCHMARK DEFINITION”, Report NEA/NSC/DOC(2013)10, OECD Nuclear Energy Agency, Nuclear Science Committee, Paris, France, 17. July 2013.
[R.4.5] F. Li, X. Jing, “Comparison of loading pattern in HTR-PM”, Proc. 2nd International Topical Meeting of HTR Technology HTR 2004, Beijing, China, September 22 – 24, 2004.
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 90
![Page 91: Design and safety approach of HTGRs - Atoms for Peace · PDF fileDesign and safety approach of HTGRs Jim C. Kuijper IAEA Training Course on High-Temperature Gas-Cooled Reactor Technology](https://reader033.vdocuments.us/reader033/viewer/2022051717/5a7018017f8b9abb538ba196/html5/thumbnails/91.jpg)
References (7)
[R.4.6] D.F. da Cruz, J.B.M. de Haas & A.I. van Heek, “ACACIA: A Small Scale Power Plant With Pebble Bed Cartridge Reactor”, Proc. International Congress on Advances in Nuclear Power Plants (ICAPP ’03), Cordoba, Spain, May 4 – 7, 2003, ISBN 0-89448-675-6.
[R.4.7] X. Yan, K. Kunitomi, T. Nakata, S. Shiozawa, “Design and development of GTHTR300”, Proc. 1st International Topical Meeting of HTR Technology HTR 2002, Petten, The Netherlands, April 22 – 24, 2002.
[R.5.1] B. Boer, J.L. Kloosterman, D. Lathouwers, T.H.J.J. van der Hagen, H. van Dam, “Optimization of a radially cooled pebble bed reactor”, Proc. 4th International Topical Meeting on High Temperature Reactor Technology HTR2008, Washington D.C., USA, September 28 - October 1, 2008.
[R.5.2] A. Marmier, M. Fütterer, K.Tucek, J.B.M. de Haas, J.C. Kuijper, and J.L. Kloosterman, “Revisiting the Concept of HTR Wallpaper Fuel”, Proc. 4th International Topical Meeting on High Temperature Reactor Technology HTR2008, Washington D.C., USA, September 28 - October 1, 2008.
19-10-2015 IAEA Training Course on HTGR Technology, Serpong, Indonesia, 19-23 October 2015 91