Science and Technology of Nuclear Installations

Review Article

International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA)

Table 1

List of CSNI international standard problems (ISPs) [2].


No.	Completion date	Title

1	1975	Standard problem 1-Edwards pipe blowdown test
2	1975	Analysis of semiscale blowdown test 11, LB LOCA
3	1977	CSNI standard problem 3; comparison of LOCA analysis codes, CISE, blowdown
4	1978	United states standard problem 6 and international standard problem 4: comparison of the standard problem calculations with measured experimental data for semiscale test S-02-6, SB LOCA
5	1979	United states standard problem 7 and international standard problem 5: final comparison report on LOFT test L1-4, LB LOCA
6	1978	ISP-6: calculations comparison report-determination of water level and phase separation effects during the initial blowdown phase
7	1979	comparison report on OECD-CSNI LOCA standard problem no. 7: analysis of a reflooding experiment, ERSEC
8	1979	Semiscale MOD1 test S-06-03 (LOFT counterpart test), LB LOCA
9	1981	LOFT test L3-1 preliminary comparison report, SB LOCA
10	1981	comparison report on OECD-CSNI LOCA standard problem no. 10: “refill and reflood experiment in a simulated PWR primary system (PKL)
11	1984	LOFT L3-5 and L3-6 comparison reports, SB LOCA
12	1982	ROSA-III 5% small break test, Run 912, BWR-SB LOCA
13	1983	international standard problem 13 (LOFT experiment L2-5) preliminary comparison report, LB LOCA
14	1985	behaviour of a fuel bundle simulator during a specified heatup and flooding period (REBEKA experiment) (results of posttest analyses)
15	1983	LOCA experiment at FIX-II facility, BWR
16	1985	rupture of a steam line within the hdr containment leading to an early two-phase flow: results of posttest analyses: final comparison report
17	1984	Marviken BWR standard problem
18	1987	LOBI-MOD2 small break LOCA experiment A2-81
19	1987	behaviour of a fuel rod bundle during a large break LOCA transient with a two-peaks temperature history (PHEBUS Experiment): final comparison report
20	1988	Doel 2 steam generator tube rupture event: final report
21	1989	PIPER-ONE experiment PO-SB-7: simulation of small and intermediate break LOCA for BWRs
22	1990	SPES-loss of feedwater transient in Italian PWR. final comparison report (1990) and evaluation of posttest analyses (1992).
23	1989	Rupture of a large diameter pipe in the HDR containment
24	1989	SURC-4-core-concrete interaction test
25	1991	ACHILLES-N2 injection from accumulators and faster (best estimate) reflood rates
26	1992	ROSA-IV LSTF-cold-leg small-break LOCA experiment
27	1992	BETHSY-small break LOCA with Loss of HP injection
28	1992	PHEBUS SFD B9+-experiment on the degradation of a PWR type core
29	1993	HDR experiment E11.2-hydrogen distribution inside the HDR containment under severe accident conditions: final comparison report
30	1992	BETA II core-concrete interaction experiment (Test V5.1): comparison report
31	1993	CORA-13 experiment on severe fuel damage
32	—	FLHT-6 experiment, cancelled
33	1994	PACTEL-VVER-440 natural circulation stepwise coolant inventory reduction
34	1994	falcon experiments FAL-ISP-1 and FAL-ISP-2, fission product transport
35	1994	NUPEC hydrogen mixing and distribution test M-7-1: final comparison report
36	1996	CORA-VVER severe fuel damage experiment (test W2)
37	1996	VANAM M3-a multi compartment aerosol depletion test with hygroscopic aerosol material-comparison report
38	1997	loss of the residual heat removal system during mid-loop operation (BETHSY)
39	1997	fuel coolant interaction and quenching (FARO)
40	1999	STORM test SR11-aerosol deposition and resuspension in the primary circuit
41	1999	RTF experiment on iodine behaviour in containment under severe accident conditions
42	2003	PANDA tests (six different phases) related to passive safety systems for advanced light water reactors
43	2001	UMCP boron dilution test
44	2002	Four open and one blind KAEVER aerosol depletion tests with three differently soluble materials and uniform thermal-hydraulic conditions with slight volume condensation
45	2003	QUENCH-06, fuel rod bundle behaviour up to and during reflood/quench (severe core damage)
46	2004	PHEBUS in reactor experiment (FP-1) on the degradation, fission product release, circuit and containment behaviour following overheating of an irradiated fuel rod bundle
47	2005	Based on experiments performed in the TOSQAN, MISTRA and ThAI facilities for containment thermal-hydraulics (e.g., gas distribution, natural convection, heat and mass distribution)
48	2005	Containment capacity (integrity and ageing of components and structures). 1 : 4 scale model of a prestressed concrete containment vessel (PCCV) of a nuclear power plant (SANDIA II mock-up)

containment analysis standard problems (CASPs)

CASP-1	1980	Comparison report on OECD-CSNI containment standard problem no. 1: “steamline rupture within a chain of compartments” (Battelle Institute test D15)
CASP-2	1982	Comparison report on OECD-CSNI containment standard problem no. 2: “water line rupture in a branched compartment chain” (Battelle Institute test D16)
CASP-3	1983	Final comparison report for containment standard problem exercise 3 (australian lucas heights blowdown/containment rig, small-scale two-compartments basic containment experiment)