A simulation of the containment activity monitor
- 1. Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations
- 2. Hydro-Quebec, Montreal, PQ (Canada)
- 3. New Brunswick Electric Power Commission, Point Lepreau, NB (Canada). Point Lepreau Generating Station
Description
The response of a containment activity monitor was predicted using a Monte Carlo approach. The estimation of count rates was based on the photon reaction rates at the sodium iodide crystal in the scintillation counter. Nine Monte Carlo simulations were done using monoenergetic sources at 4.95, 2.05, 1.55, 1.00, 0.72, 0.52, 0.40, 0.32, and 0.20 MeV. The simulations were performed using the model of an experimental setup of the Gentilly-2 Nuclear Generating Station vapour recovery exhaust pipe. The simulation results were post-processed into a database for use in an interactive program we developed called CRATES. CRATES accepts all radionuclides that are in the RADDECAY library. It estimates the count rates in the exhaust pipe by interpolating among the nine monoenergetic source spectra. The accuracy of the estimation was tested against experimental measurements for radionuclides 131I, 137Cs, and 60Co. The use of the computer program CRATES to predict count rates at the containment activity monitor for a hypothetical situation was discussed. 8 refs., 3 figs., 4 tabs
Additional details
Publishing Information
- ISBN
- 0-919784-31-3
- Imprint Title
- Canadian Nuclear Society/American Nuclear Society 4. international conference on simulation methods in nuclear engineering
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.1) [15 p.].
- Report number
- INIS-mf--14622
Conference
- Title
- 4. international conference on simulation methods in nuclear engineering.
- Dates
- 2-4 Jun 1993.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 26073925
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; CALIBRATION; CESIUM 137; COBALT 60; COMPUTERIZED SIMULATION; CONTAINMENT; FISSION PRODUCTS; IODINE 131; MONTE CARLO METHOD; NAI DETECTORS; POINT LEPREAU-1 REACTOR; RADIATION MONITORS; REACTOR MONITORING SYSTEMS; VENTILATION SYSTEMS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; CANDU TYPE REACTORS; CESIUM ISOTOPES; COBALT ISOTOPES; COMPUTER CODES; DAYS LIVING RADIOISOTOPES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IODINE ISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MEASURING INSTRUMENTS; MINUTES LIVING RADIOISOTOPES; MONITORS; NATURAL URANIUM REACTORS; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION DETECTORS; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTORS; SCINTILLATION COUNTERS; SIMULATION; SOLID SCINTILLATION DETECTORS; THERMAL REACTORS; YEARS LIVING RADIOISOTOPES