NUREG-1537, Part 2 - NRC

CHAPTER 4
4.5.2 Reactor Core Physics Parameters
Areas of Review
In this section of the SAR, the applicant should present information on core
physics parameters that determine reactor operating characteristics and are
influenced by the reactor design. The principal objective of a non-power reactor is
to obtain a radiation source that conforms to requirements for use, but does not
pose an unacceptable risk to the health and safety of the public. By proper design,
the reactor will operate at steady or pulsed power and the reactor systems will be
able to terminate or mitigate transients without reactor damage. The areas of
review should include the design features of the reactor core that determine the
operating characteristics and the analytical methods for important contributing
parameters. The results presented in this section of the SAR should be used in
other sections of this chapter.
The areas of review are discussed further in this section of the format and content
guide.
Acceptance Criteria
The acceptance criteria for the information on reactor core physics parameters
include the following:
* The calculational assumptions and methods should be justified and
traceable to their development and validation, and the results should be
compared with calculations of other similar facilities and previous
experimental measurements. The ranges of validity and accuracy should be
stated and justified.
* Uncertainties in the analyses should be provided and justified
* Methods used to analyze neutron lifetime, effective delayed neutron
fraction, and reactor periods should be presented, and the results should be
justified. Comparisons should be made with similar reactor facilities. The
results should agree within the estimates of accuracy for the methods.
* Coefficients of reactivity (temperature, void, and power) should all be
negative over the significant portion of the operating ranges of the reactor.
The results should include estimates of accuracy. If any parameter is not
negative within the error limits over the credible range of reactor operation,
the combination of the reactivity coefficients should be analyzed and shown
to be sufficient to prevent reactor damage and risk to the public from
reactor transients as discussed in Chapter 13 of the SAR.
NUREG-1 537, P 2 4-22 REv 0,2/96
NUREG-1537,PART2 4-22 REV 0 2/96
- R_