L.N.Topilski(1), D.A.Petti(2), T.Inabe(3), W.Gulden(4), B.Merrill(2), S.Polkinghorne(2), R.Moore(2), J.M.Gay(5), R.Blomquist(6), Y.Seki(3), R.Kurihara(3), T.Kunugi(7), K.Takase(7)
(1) ITER Joint Central Team, 11025 North Torrey Pines Rd., La Jolla, CA 92037
(2) Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental Laboratory, P.O. Box 1625, Idaho Falls, Idaho 83415
(3) JAERI, Naka Fusion Research Establishment, Mukoyama 801-1, Naka-machi, Naka-gan, Ibaraki-ken, 311-01, Japan
(4) The NET team, Boltzmannstrasse 2, D-85748 Garching, Germany
(5) Technicatome, Service d'Etudes physiques et de Surete, Rue A.Ampere, B.P.34000, France
(6) Studsvik ECO&Safety AB, S-611 82, Nykoping, Sweden
(7) JAERI, Department of Reactor Engineering, Tokai-mura, Ibaraki-ken, 319-11, Japan
This paper summarizes principal, process, status, and some examples of validation and verification (V&V) of ITER computer codes that are being used in safety analyses.
The safety computer codes have to be verified and validated to ensure that computer code results are meaningful and correctly reflects the reality. Verification is the process of determining whether or not the software is coded correctly and conforms to the specified software requirements. Validation is the process of evaluating software to ensure compliance with physical applicability to the process. Validation of a code would consist of comparing it with known analytical solutions or against an already validated computer code, or could include benchmarking the code against relevant experimental data.
ITER initiated a validation activity for codes used for accident analyses in case of water coolant ingress in the vacuum vessel and in case of loss of vacuum events. Japanese home team accomplished tests on ICE (Ingress of Coolant Event) and on LOVA (Lost Of VAcuum) facilities. The test results were compared with pre-test calculational results obtained by different codes, such as MELCOR, INTRA, PAX, TRAC-BF1, and CONSEN.
Partial V&V information provided for the codes used for NSSR-2 safety analyses and the results of ICE and LOVA validation studies will be presented in this paper.