RIA Scoping Test Experiment Specification Document

RIA Scoping Test Experiment Specification Document

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Published: 1977

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The experiment requirements and objectives for the reactivity initiated accident (RIA) tests to be conducted in the Power Burst Facility (PBF) are described 1n the RIA Experiment Requirements Document (ERD) The primary objectives of the RIA research are to determine fuel failure thresholds, modes and consequences as functions of enthalpy insertion, irradiation history, and fuel design. Coolant conditions of pressure, temperature, and flow rate that are typical of hot-startup conditions in commercial BWRs will be used in the Series 1 tests. The first R!A test outlined in the ERD, RIA 1-1, is to be performed using four test fuel rods (two unirradiated and two irradiated) in the four rod hardware. The test fuel rods are to be exposed to a power transient in PBF which deposits an anergy of about 300 cal/g at 90% of the fuel radius (i.e. near the fuel surface). This will be the first RIA experiment ever perfonned at hot startup conditions and three potential problems have been identified since the ERD was written. These problem areas are: identification of the fuel failure threshold energy deposition for hot-startup conditions, evaluation of calorimetry techniques for RIA transient tests, and determination of possible pressure pulses that can result from fuel failure in a water filled system. Also, recent TREAT test results have indicated that it may be difficult to obtain usable information from some of the instruments planned for use on the Ser1es 1 tests. To resolve the questions raised by the TREAT tests it will be necessary to expose selected instruments to a power burst and monitor their response under adiabatic, constant pressure conditions. Consideration of these potential problems made it clear that an RIA Scoping Test, the subject of this Experiment Specification Document, must be perforrned to resolve thest: potential problems prior to perfonnance of test RIA 1-1. The RIA Scop1ng Test should be comprised of five single rod experiments. The first rod will be subjected to a series of transient power bursts of ever increasing energy reIease to determine the energy deposition failure threshold. The second rod will be subjected to an energy deposition about 50 cal/g less than the energy deposition required for failure during the first test. The third rod will be tested at the failure threshold energy deposition. A calorimetric·power calibration will be performed on the second and third rods for comparison purposes. Rods four and five will be subjected to very high energy depositions (475 and 600 cal/g average energy insertion, respectively) to evaluate pressure pulse generation due to fuel fragmentation at hot-startup conditions. Calorimetric power calibrations will be performed on rods four and five. In the event of unexpectedly large pressure pulse generation for rods four and five it may be necessary to perform additional high energy deposition tests to determine the energy deposition required for fuel dispersal and subsequent pressure pulse generation. The PBF-TFBF singla rod test train or its equivalent will be used for the scoping tests. lnstrumentation for measurement of pressure pulse generation and test rod power will be necessary for the test. To evaluate the effects of radiation on the performance of the fuel rod instrumentation planned for the RlA Series 1 tests, two pressure sensors and an LVDT should be placed in a nearly adiabatic, constant pressure envirorment within the test train and monitored during the bursts. No test rod instrumentation will be required. Results of the Lead Rod Test Series will be used to make preliminary estimates of the transient burst period required.


Reactivity Initiated Accident Test Series RIA Scoping Test Experiment Operating Specification

Reactivity Initiated Accident Test Series RIA Scoping Test Experiment Operating Specification

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Published: 1978

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This document describes the experiment operating specifications for the Reactivity Initiated Accident (RIA) Scoping Test to be conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The primary objectives of the RIA research are to determine fuel failure thresholds, modes, and consequences as functions of (a) enthalpy insertion, (b) irradiation history, and (c) fuel design. Coolant conditions of pressure, temperature, and flow rate that are typical of hot-startup conditions in commercial boiling water reactors (BWRs) will be used in the first six RIA tests, termed Series I.


RIA 1-4 Experiment Specification Document

RIA 1-4 Experiment Specification Document

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Published: 1978

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The Reactivity Initiated Accident (RIA) test series is being performed in the Power Burst Facility (PBF) to provide data for verifying analytical codes capable of predicting light water reactor fuel performance during hypothetical control rod drop (or ejection) accidents. The most important aspect of an RIA or an RIA test is the magnitude of energy deposited into the fuel, therefore the primary purpose of the RIA test series is to better define the relationship between e.nergy deposition and fuel rod behavior. In particular, the RIA research objectives are to determine failure thresholds, modes, and consequences with respect to total energy deposition, irradiation history, and fuel design. The most severe RIA is the postulated Boiling Water Reactor (BWR) control rod drop during reactor startup, therefore all the RIA tests will be conducted at BWR startup coolant conditions. Test RIA 1-4 will consist of a 4 x·4 array of rods positioned in a coolant flow shroud. Fourteen of the rods are unirradiated BWR/6-type fuel rods and two are water-filled rods. Two water rods will be interior rods positioned along one diagonal. The primary objective of Test RIA 1-4 will be to obtain data on clustered fuel rod behavior during a rapid power transient simulating a BWR control rod drop. This document provides a basis for understanding the test plan for Test RIA 1-4. Past RIA test experience and a review of the PBF-RIA tests which are scheduled for completion prior to Test RIA 1-4 are summarized. The fuel rod, water rod, grid spacer, flow channel, and bundle support structure specifications are described. The instrumentation required for this test is discussed. The preliminary reactor operation and posttest operation requirements are presented.


Reactivity Initiated Accident Test Series Test RIA 1-2 Experiment Operating Specification

Reactivity Initiated Accident Test Series Test RIA 1-2 Experiment Operating Specification

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Published: 1978

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This document describes the experiment operating specifications for the Reactivity Initiated Accident (RIA) Test RIA 1-2 to be conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The RIA Series I research objectives are to determine fuel failure thresholds, modes and consequences as functions of enthalpy insertion, irradiation history, and fuel design. Coolant conditions of pressure, temperature, and flow rate that are typical of hot-startup conditions in commercial boiling water reactors {BWRs) will be used. The second test in Series I, Test RIA 1-2, will be comprised of four individual rods, each surrounded by a separate flow shroud. The four rods will be preirradiated. The specific objectives of the test are to: (1) characterize the response of preirradiated fuel rods during a RIA event conducted at BWR hot-startup conditions and (2) evaluate the effect of internal rod pressure on preirradiated fuel rod transient response. The test sequence will begin with steady state power operation to condition the fuel (pellet cracking and relocation) and determine the fuel rod power calibration. The loop will then be cooled down, the test train removed from the in-pile tube, and the cobalt flux wires that are mounted on each flow shroud will be replaced. The transient fuel rod energy deposition for the Test RIA 1-2 rods will be chosen from the fuel rod response vs. energy deposition observed in the first three phases of the RIA Scoping Test and the first test of Series J, Test RIA 1-1. The design of the test fuel rods, test assembly, and instrumentation associated with Test RIA 1-2 are described. The planned experiment conduct for the test is described. The data recording and reduction requirements are provided. The posttest operations support and the postirradiation examination requirements associated with Test RIA 1-2 are described.


RIA 1-2 Experiment Specification Document

RIA 1-2 Experiment Specification Document

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Published: 1977

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The current status of Reactivity Initiated Accident (RIA) irradiated fuel behavior knowledge, based primarily on the review of the NSRR and SPERT data and the fuel rod modeling studies presented in the Experiment Requirements Document (ERD), is discussed. The hardware specifications are provided, including the test assembly and the test rods. The measurement requirements needed to meet the objectives of the test are presented. Some of the reactor operation requirements associated with the RIA 1-2 test are listed.


Reactivity Initiated Accident Test Series Test RIA 1-1 Experiment Operating Specification

Reactivity Initiated Accident Test Series Test RIA 1-1 Experiment Operating Specification

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Published: 1978

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This document describes the experiment operating specifications for the Reactivity Initiated Accident (RIA) Test RIA 1-1 to be conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The RIA Series I research objectives are to determine fuel failure thresholds, modes and consequences as functions of enthalpy insertion, irradiation history, and fuel design. Coolant conditions of pressure, temperature, and flow rate that are typical of hot-startup conditions in commercial boiling water reactors (BWRs) will be used. The first test in Series I, Test RIA 1-1, will be comprised of four individual rods, each surrounded by a separate flow shroud. Two rods will be preirradiated and two rods will be unirradiated. The specific objectives of the test are to: (1) characterize the response of unirradiated and preirradiated fuel rods during a RIA event conducted at BWR hot-startup conditions and (2) evaluate test instrumentation response during an RIA. The test sequence will begin with steady state power operation to condition the fuel (pellet cracking and relocation) and determine the fuel rod power calibration. The loop will then be cooled down, the test train removed from the in-pile tube, and one of the unirradiated rods will be removed for fission product analysis and replaced with an identical unirradiated rod. The transient fuel rod energy deposition for Test RIA 1-1 will be chosen from the fuel rod response vs. energy deposition data observed in the first three phases of the RIA Scoping Test. It is anticipated that a fuel pellet surface energy deposition of about 1100 J/g will be required to ensure cladding failure of all four rods. The design of the test fuel rods, test assembly, and instrumentation associated with Test RIA 1-1 are described. The experiment conduct for the test is described. The data recording and reduction requirements are provided. The posttest support and the postirradiation examination requirements associated with Test RIA 1-1 are described.