Background and purpose
This international benchmark, concerns Pebble-Bed Modular Reactor
(PBMR) coupled neutronics/thermal hydraulics transients based on the
PBMR-400MW design. The deterministic neutronics, thermal-hydraulics and
transient analysis tools and methods available to design and analyse
PBMRs lag, in many cases, behind the state of the art compared to other
reactor technologies. This has motivated the testing of existing
methods for HTGRs but also the development of more accurate and
efficient tools to analyse the neutronics and thermal-hydraulic
behaviour for the design and safety evaluations of the PBMR. In
addition to the development of new methods, this includes defining
appropriate benchmarks to verify and validate the new methods in
computer codes.
The scope of the benchmark is to establish well-defined problems, based
on a common given set of cross sections, to compare methods and tools
in core simulation and thermal hydraulics analysis with a specific
focus on transient events through a set of multi-dimensional
computational test problems.
The benchmark exercise has the following objectives:
- Establish a standard benchmark for coupled codes
(neutronics/thermal-hydraulics) for PBMR design
- Code-to-code comparison using a common cross section
library
- Obtain a detailed understanding of the events and the
processes
- Benefit from different approaches, understanding
limitations and approximations
Major Design and Operating
Characteristics of the PBMR
| PBMR Characteristic |
Value |
| Installed thermal
capacity |
400
MW(t) |
| Installed electric
capacity |
165MW(e) |
| Load following
capability |
100-40-100% |
Availability
|
>
=
95% |
| Core configuration |
Vertical
with fixed centre
graphite reflector |
| Fuel
|
TRISO
ceramic coated U-235 in graphite spheres |
| Primary coolant |
Helium |
| Primary coolant
pressure |
9MPa |
Moderator
|
Graphite |
| Core outlet
temperature |
900°C. |
Core inlet
temperature
|
500°C |
| Cycle type |
Direct
|
| Number of circuits |
1
|
| Cycle efficiency |
>=
41% |
| Emergency planning
zone |
400
meters |
The PBMR functions under a direct Brayton cycle with primary coolant
helium flowing downward through the core and exiting at 900°C. The
helium then enters the turbine relinquishing energy to drive the
electric generator and compressors. After leaving the turbine, the
helium then passes consecutively through the LP primary side of the
recuperator, then the pre-cooler, the low pressure compressor,
intercooler, high pressure compressor and then on to the HP secondary
side of the recuperator before re-entering the reactor vessel at
500°C. Power is adjusted by regulating the mass flow rate of gas
inside the primary circuit. This is achieved by a combination of
compressor bypass and system pressure changes. Increasing the pressure
results in an increase in mass flow rate, which results in an increase
in the power removed from the core. Power reduction is achieved by
removing gas from the circuit. A Helium Inventory Control System is
used to provide an increase or decrease in system pressure.
The PBMR-400 benchmark consists of two parts (phases), each part
consisting
of different exercises:s:
- Phase I: Steady State Benchmark Calculational Cases
Exercise 1: Neutronics Solution
with Fixed Cross Sections
Exercise 2: Thermal Hydraulic solution with given power / heat sources
Exercise 3: Combined neutronics thermal hydraulics calculation -
starting condition for the transients
- Phase II: Transient Benchmark
Exercise 1: Depressurised Loss of
Forced Cooling (DLOFC) without SCRAM
Exercise 2 : Depressurised Loss of Forced Cooling (DLOFC) with SCRAM
Exercise 3: Pressurised Loss of Forced Cooling (PLOFC) with SCRAM
Exercise 4 : 100-40-100 Load Follow
Exercise 5 : Fast Reactivity Insertion - Control Rod Withdrawal (CRW)
and Control Rod Ejection (CRE) scenarios at hot full power conditions
Exercise 6 : Cold Helium Inlet
Reference
Frederik Reitsma, Kostadin
Ivanov,Tom Downar, Han de Haas, Sonat
Sen, Gerhard Strydom, Ramatsemela Mphahlele, Bismark Tyobeka, Volkan
Seker, Hans D Gougar: PBMR Coupled Neutronics/Thermal Hydraulics
Transient Benchmark - The PBMR-400 Core Design, Benchmark Definition,
Draft V03, to be published by OECD in 2005
Material available to
participants on CD-ROM
Records of meetings
- Proceedings
of the first workshop (PBMRT1)
- Summary
of the
First workshop, Paris, 16-17 June 2005
(PBMRT1)
- Proposed
Agenda for Ad-hoc meeting, Avignon, 13 September 2005 (PBMRT1.5)
- Proposed Agenda
for
Second workshop (PBMRT2) OECD/NEA Issy les Moulineaux, France, 26-27
January 2006
- Update
concerning the Benchmark (20
October 2006)
- Proceedings of the
second workshop (PBMRT2)
- Summary of
Second workshop, Issy les Moulineaux, 26-27 January 2006
- Proposed
Agenda for Third workshop (PBMRT3) OECD/NEA Issy les Moulineaux,
France, 1-2 February 2007
- Summary of Third workshop
(PBMRT3) OECD/NEA Issy les Moulineaux, France, 1-2 February 2007
Benchmark
Specification
- Updated
Benchmark specifications document Draft
V107 (dated 20 June 2007)
- The Simplified Cross
Section Set:
"OECD-PBMR400-Simplified.XS"
- Decay Heat Values
(12 December 2006)
- The multi-dimensional interpolation
routine
"lint5d.for"
- Sample Excel spreadsheets to report
results for steady-states (1, 2, 3) and transient cases (1,
2,
3, 4a, 4b, 5a, 5b, 5c, 5d, 6) (20
June 2007), zipped Excel
spreadsheets
- Questionnaire
for submitting results for OECD PBMR-400 Benchmark (Word) (20 August 2007)
Latest comparisons of results for Exercises 1, 2
and 3 of the
PBMR-400 benchmark (
update:
14 December 2006)
Action List
Archived
information
- Library “OECD-PBMR400.XS” that contains cross sections as a
function of fuel and moderator temperatures, xenon concentrations, and
fast and thermal buckling values (42 Mbytes). (Superceded)
- Library “OECD-PBMR400-NoBuck.XS” that contains no buckling
dependencies, only fuel and moderator temperature and xenon
concentration dependencies (5 Mbytes). (Superceded)